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Remediation Work Plan 1110-PP-001 Rev. 0
Prepared for:
Cardinal Health PET Cyclotron Facility St Louis, MO
August 2016
Prepared by:
9111 Cross Park Drive, Suite D200 Knoxville, TN 37923
800.563.7497
1110-PP-001, Rev. 0 August 2016
Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO
RECORD OF REVISIONS
Change Number
Date Description of Change Approval
0 9/12/16 Initial Distribution
APPROVALS Prepared By ________________________________________ ____9/12/16__ Tom Hansen III Date Approved By ________________________________________ ____9/12/2016_ Timothy Pratt Date Review and Approval ________________________________________ ______________ Cardinal Health Date
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Table of Contents 1. PURPOSE ............................................................................................................................. 1
2. FACILITY OPERATING HISTORY ............................................................................................ 1
3. FACILITY DESCRIPTION ........................................................................................................ 2
4. RADIOLOGICAL STATUS OF FACILITY .................................................................................. 3
5. RELEASE CRITERION AND DOSE MODELING ....................................................................... 6 5.1. Structure DCGLs for Activated Areas ............................................................................. 6 5.2. Surface DCGLs for Non-Activated Areas ........................................................................ 8 6. PLANNED DECOMMISSIONING ACTIVITIES ......................................................................... 9 6.1. Characterization ............................................................................................................10 6.2. Remediation ..................................................................................................................13 6.3. Air Sampling and Concrete Dust Control .......................................................................13 6.4. Survey and Removal of Clean Concrete Debris .............................................................14
7. PROJECT MANAGEMENT AND ORGANIZATION ................................................................ 14 7.1. Project Manager (PM) ...................................................................................................14 7.2. Field Personnel .............................................................................................................15 7.3. Coordination of Efforts ...................................................................................................16 8. HEALTH AND SAFETY PROGRAM DURING DECOMMISSIONING ...................................... 16
9. SURVEY INSTRUMENTATION ............................................................................................ 17 9.1. Instrument Calibration ...................................................................................................17 9.2. Daily Response Checks ................................................................................................17 9.3. Determination of Counting Times and Minimum Detectable Concentrations ..................17 9.3.1. Static Counting ....................................................................................................17 9.3.2. Ratemeter Scanning ............................................................................................18 9.3.3. Gamma Scans .....................................................................................................18 9.3.4. Removable Contamination Measurement Counting .............................................21 9.4. Counting Uncertainty .....................................................................................................21 9.5. Instrumentation Specifications .......................................................................................22 9.6. Background Determination ............................................................................................23
10. RADIOACTIVE WASTE MANAGEMENT PROGRAM ............................................................ 23 10.1. Waste Characterization .................................................................................................23 10.2. Waste Shipment ............................................................................................................23 11. QUALITY ASSURANCE PROGRAM...................................................................................... 23
12. FACILITY RADIATION SURVEYS .......................................................................................... 25 12.1. Data Quality Objectives .................................................................................................25 12.2. Area Classification .........................................................................................................26 12.3. Survey Unit Identification ...............................................................................................27 12.4. Surface Scans ...............................................................................................................28 12.5. Determining the Number of Sample Locations ...............................................................28 12.5.1. Number of Gross Beta/Gamma Total Surface Activity Measurements .................29 12.5.2. Number of Volumetric NaI Measurement Locations .............................................29 12.6. Determination of Sampling Locations ............................................................................30 12.7. Total Surface Activity Measurements ............................................................................31 12.8. Gamma Radiation Measurements .................................................................................31 12.9. Removable Contamination Measurements ....................................................................32 12.10. Volumetric Core Samples ..............................................................................................32 12.11. Survey Investigation Levels for Non-Activated Surfaces ................................................32 12.12. Survey Investigation Levels for Potentially Activated Structures ....................................32
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12.13. Survey Documentation ..................................................................................................33 12.14. Data Validation ..............................................................................................................33
13. EVALUATING SURVEY RESULTS ......................................................................................... 34
14. FINAL REPORT ................................................................................................................... 34
15. REFERENCES ...................................................................................................................... 35
Attachments Attachment 1: Laboratory Sample Analysis Reports for Cyclotron Room Characterization Attachment 2: RESRAD-BUILD DCGLactivation Modeling for Radionuclides of Concern Attachment 3: RESRAD-BUILD DCGLsurface Modeling for Radionuclides of Concern Attachment 4: MicroShield MDC Model Abbreviations and Acronyms ALARA As Low As Reasonably Achievable Ameriphysics Ameriphysics, LLC CFR Code of Federal Regulations cpm counts per minute DAC Derived Air Concentration DCGL Derived Concentration Guideline Level dpm disintegration per minute DQO Data Quality Objective ICRP International Commission on Radiological Protection LBGR Lower Bound of the Gray Region MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration MO DOH Missouri Department of Health NaI Sodium Iodide NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission PET Positron Emission Tomography QAPP Quality Assurance Project Plan TEDE Total Effective Dose Equivalent
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1. PURPOSE The purpose of this Remediation Work Plan (Plan) is to provide the concise work instructions necessary to decommission the Cardinal Health PET Manufacturing Facility located at 10718 Trenton Avenue, St Louis, MO. Cardinal Health has contracted Ameriphysics, LLC (Ameriphysics) via Rowe Transfer Inc. to perform the decommissioning and survey activities described in this Plan. All work will be accomplished using Ameriphysics’ Nuclear Regulatory Commission (NRC) radioactive material license. Activities necessary to accomplish decommissioning include radiological characterization, remediation where residual volumetric contamination exceeds release criterion, transportation of resultant wastes for disposal, and final status surveying to demonstrate compliance with the NRC's release criterion. This Plan was developed using the guidance provided in NUREG-1757, “Consolidated NMSS Decommissioning Guidance” and NUREG-1575, “Multi-Agency Radiation Survey and Site Investigation Manual” (MARSSIM), and provides the approach, methods, and techniques for the radiological decommissioning of the facility. These methods ensure technically defensible data are generated to aid in determining compliance with the release criterion for unrestricted use specified in 10 CFR 20 Subpart E, Section 20.1402, Radiological criteria for unrestricted use. 2. FACILITY OPERATING HISTORY The Cardinal Health PET Manufacturing facility on Trenton Avenue is currently licensed by the NRC for possession and storage of radioactive materials with the intent to decommission. The current license amendment was issued on January 14, 2016. The facility was previously licensed under the same Radioactive Materials License number for the production, packaging, and distribution of manufactured radiopharmaceuticals and for possession and storage of radioactive materials incident to the manufacture of radiopharmaceuticals by use of a cyclotron. This facility was opened by Syncor Advanced Isotopes in 2001 and the site was registered with the Missouri Department of Health (MO DOH) for accelerator-produced materials under registration IRM-141. Following Cardinal Health’s acquisition of Syncor, the MO DOH updated this registration with the Cardinal Health name. Cardinal Health then applied for a Radioactive Materials License with the NRC in 2011 as a result of the NRC implementing jurisdiction over accelerator-produced materials under the Energy Policy Act of 2005. This license was granted on December 27, 2011 under the current license number. The cyclotron at this facility is a General Electric PETtrace 8, which primarily produced F-18 to be used in radiopharmaceuticals for Positron Emission Tomography (PET) scans. The cyclotron typically operated at an energy of 16.5 MeV. The cyclotron is encased in a concrete vault which shielded the machine in all six primary directions.
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This cyclotron primarily used O-18 as its target material, generating F-18 and neutrons through a (p,n) reaction; these neutrons create the potential for activation of the surrounding materials, primarily the cyclotron vault and the cyclotron itself. The cyclotron and components were shipped to Michigan State University on 8/24/2016. All remaining wastes were shipped for processing and disposal on 9/7/2016. 3. FACILITY DESCRIPTION The site is located in an industrial park at 10718 Trenton Ave., St Louis, MO. Figure 3-1 provides a satellite view of the Cardinal Health PET Manufacturing facility location. The footprint of the facility is outlined in blue. The map was obtained online from Google maps. Figure 3-2 provides the floor plan of the facility with the Restricted Area outlined with bold lines.
Figure 3-1– Location of Cardinal Health PET Manufacturing Facility
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Figure 3-2– Layout of the Cardinal Health St louis, MO Facility
4. RADIOLOGICAL STATUS OF FACILITY The site produced F-18 as a result of normal operations. This radionuclide has a very short half-life (110 minutes), and since the site has not operated since August 14, 2015, any residual F-18 has decayed. The reaction that produces F-18, 18O(p,n)18F, also produces neutrons that can cause building materials in the cyclotron room to become activated, primarily concrete and steel. The cool down period has allowed very short-lived radionuclides to decay; however, the radionuclides in Table 4-1 may be present in the floor, wall, and ceiling of the cyclotron vault.
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Since the PETtrace cyclotron was shielded by a concrete vault, there is very little likelihood that any other surfaces in the facility have been activated. The concentration varies according to proximity to the beam and interferences that cause losses.
Table 4-1: Potential Radiological Contaminants
Atomic Number Element Radionuclide(s)
3 Tritium 3H
11 Sodium 22Na
21 Scandium 46Sc
24 Chromium 51Cr
25 Manganese 54Mn
26 Iron 55Fe, 59Fe
27 Cobalt 56Co, 57Co, 58Co, 60Co
30 Zinc 65Zn
41 Niobium 95Nb
47 Silver 108mAg, 110mAg
48 Cadmium 109Cd
51 Antimony 124Sb
55 Cesium 134Cs
63 Europium 152Eu, 154Eu, 155Eu
Radionuclides of concern from Table 4-1 and certain properties of their decay from ICRP Publication 107, “Nuclear Decay Data for Dosimetric Calculations”, are presented in Table 4-2.
Table 4-2: Radionuclides of Concern and Properties of Decay
Nuclide Half-Life1 Daughter
Decay Mode2 Fraction
Energy Emitted (MeV/transformation)
Alpha Electron Photon Total
H-3 12.32 y
He-3 B-
1.00 - 0.005 - 0.0057
Na-22 2.6019 y
22Ne EC, B+ 1.00
- 0.1941 2.1926 2.3866
Sc-46 83.79 d
46Ti B-
1.00 - 0.1121 2.0096 2.1217
Cr-51 27.7025 d
51V EC
1.00 - 0.0038 0.0329 0.0367
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Nuclide Half-Life1 Daughter
Decay Mode2 Fraction
Energy Emitted (MeV/transformation)
Alpha Electron Photon Total
Mn-54 313.12 d
54Cr 54Fe
EC, B+, B- 1.00
2.90E-06 - 0.0042 0.8360 0.8402
Fe-55 2.737 y Mn-55
EC 1.00
0.0042 0.0017 0.0058
Fe-59 44.495 d
59Co B-
1.00 - 0.1179 1.1883 1.3062
Co-56 77.23 d
56Fe EC, B+ 1.00
- 0.1198 3.6404 3.7602
Co-57 271.74 d
57Fe EC
1.00 - 0.0186 0.1252 0.1439
Co-58 70.86 d
58Fe EC, B+ 1.00
- 0.0340 0.9749 1.0089
Co-60 05.2713 y
60Ni B-
1.00 - 0.0969 2.5038 2.6007
Zn-65 244.06 d
65Cu EC, B+ 1.00
- 0.0069 0.5819 0.5888
Nb-95 34.991 d
95Mo B-
1.00 - 0.0446 0.7645 0.8091
Ag-108m 418 y 108Ag 108Pd
EC, IT 8.70E-02 9.13E-01
- 0.0159 1.6209 1.6368
Ag-110m 249.76 d
110Ag 110Cd
B-, IT 1.36E-02 9.86E-01
- 0.0758 2.7606 2.8363
Cd-109 461.4 d
109Ag EC
1.00 - 0.0827 0.0265 0.1092
Sb-124 60.20 d
124Te B-
1.00 - 0.3831 1.8531 2.2362
Cs-134 2.0648 y
134Ba 134Xe
B-, EC 1.00
3.00E-06 - 0.1639 1.5551 1.7190
Eu-152 13.537 y
152Gd 152Sm
EC, B+, B- 2.79E-01 7.21E-01
- 0.1286 1.1759 1.3045
Eu-154 8.593 y
154Gd 154Sm
B-, EC 9.998E-01 2.000E-04
- 0.2730 1.2493 1.5223
Eu-155 4.7611 y
155Gd B-
1.00 - 0.0647 0.0612 0.1259
1 Key to half-life: d is days and y is years 2 Key to decay mode: B- is beta minus, B+ is beta plus, EC is electron capture
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All daughter nuclides are stable, with the exception of Ag-108, Ag-110 and Gd-152. Activity contributions from these daughters are considered negligible as Ag-108 is formed by isomeric transition in only 8.7% of Ag-108m transformations, Ag-110 is formed by isomeric transition in only 1.36% of Ag-110m transformations, and Gd-152 has a very long half-life, 1.08E+14 years. Radiation emitted is beta and gamma; however, it is important to consider that atoms undergoing decay are trapped within the volume of the materials and surfaces. According to the Radiological Health Handbook, the maximum range of a 1 MeV beta particle is less than 1/10th of an inch in lead, copper, iron, aluminum, and concrete. At 0.1 MeV, the maximum range is less than 1/100th of an inch. Unlike betas and other charged particles that exhibit finite ranges, gammas cannot be completely attenuated. Rather, the intensity of the radiation is reduced by increasingly thicker absorbers. Consequently, gamma radiation is the radiation of concern except in instances where surface contamination is a concern. 5. RELEASE CRITERION AND DOSE MODELING Radiological requirements for license termination are described Title 10 of the Code of Federal Regulations, Part 20, Subpart E, Radiological Criteria for License Termination, which states that a site will be considered acceptable for unrestricted release if the residual radioactivity that is distinguishable from background radiation results in a total effective dose equivalent (TEDE) to an average member of the critical group that does not exceed 25 millirem per year (mrem/y), and the residual radioactivity has been reduced to levels that are as low as reasonably achievable (ALARA). The release criterion is dose-based and cannot be measured directly. Consequently, MARSSIM uses the term derived concentration guideline value (DCGL) to describe radionuclide-specific surface or volume residual radioactivity levels that corresponds to the release criterion. This project requires DCGLs for volumetrically activated structures (DCGLactivation) and non-activated surfaces that could have been potentially surface contaminated by the transfer of contamination from materials moved and stored in these areas (DCGLsurface). Dose modeling software, RESRAD-BUILD (Argonne National Laboratory), V3.50, October 30, 2009, was used to establish DCGLs in both instances. 5.1. Structure DCGLs for Activated Areas The RESRAD-BUILD code was run using the code’s default parameters to determine the maximum dose in mrem per year to an individual from 1 pCi/g of each of the listed nuclides distributed volumetrically throughout a material. Values for DCGLactivation were determined by dividing the release criterion, 25 mrem/yr, by the code’s outputs. The RESRAD-BUILD output reports are included in Attachment 2. The dose per pCi/g values returned by the code and the corresponding DCGLactivation are provided in Table 5-1.
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Table 5-1: DCGLactivation for Concrete Structures
Radionuclide mrem/yr
pCi/g DCGL (pCi/g)
Ag-108m 3.06E+00 8.17E+00
Ag-110m 3.38E+00 7.40E+00
Cd-109 3.14E-03 7.96E+03
Co-56 1.23E+00 2.03E+01
Co-57 9.51E-02 2.63E+02
Co-58 1.72E-02 1.45E+03
Co-60 4.62E+00 5.41E+00
Cr-51 6.11E-03 4.09E+03
Cs-134 2.54E+00 9.84E+00
Eu-152 2.12E+00 1.18E+01
Eu-154 2.28E+00 1.10E+01
Eu-155 4.53E-02 5.52E+02
Fe-55 1.16E-08 2.15E+09
Fe-59 9.26E-03 2.70E+03
H-3 9.67E-03 2.59E+03
Mn-54 1.11E+00 2.25E+01
Na-22 3.76E+00 6.65E+00
Nb-95 1.10E-01 2.27E+02
Sb-124 4.13E-03 6.05E+03
Sc-46 1.46E-08 1.71E+09
Zn-65 7.12E-01 3.51E+01
Note that the “sum of fractions” rule applies. The instruments used for surface scans will not be able to discriminate between radionuclides; therefore, a gross activation DCGL (DCGLgross) is determined using the MARSSIM Equation 4-4:
n
ngross
DCGL
f
DCGL
f
DCGL
fDCGL
2
2
1
1
1
To determine DCGLgross, the data from characterization-sample location "Cyclotron Vault Floor (0-6 inch)" in section 6.1 was used to determine the activity fraction (fn). The activity contribution from each radionuclide was summed, and the activity fraction that each radionuclide contributes to the total activity was determined. The results were input into the following table, and MARSSIM Equation 4-4 was used to calculate the DCGLgross.
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Table 5-2: Volumetric DCGLgross Determination
Radionuclide Fraction of Total
(fn) DCGL (pCi/g)
Activity Fraction
(fn/DCGL)
Co-60 23.2% 5.41E+00 4.29E-02
Cs-134 2.8% 9.84E+00 2.88E-03
Eu-152 63.0% 1.18E+01 5.35E-02
Eu-154 6.4% 1.10E+01 5.87E-03
Mn-54 1.8% 2.25E+01 8.16E-04
Sc-46 1.2% 1.71E+09 6.75E-12
Zn-65 1.5% 3.51E+01 4.28E-04
Σfn/DCGL 1.06E-01
DCGLgross in pCi/g (1/Σfn/DCGL) 9.41E+00
Note that DCGLgross is applied only when making gross measurements. In instances where radionuclide-specific measurements are performed to demonstrate compliance with the release criterion, results will be compared against the radionuclide-specific DCGLs indicated in column 3 of Table 5-1. Sum of fractions will be observed, and the combined results may not exceed unity., Small localized hotspots that exceed the DCGL could still result in the survey unit, as a whole, meeting the release criterion. This would require the use of the elevated measurement comparison methodology discussed in MARSSIM sections 8.5.1 and 8.5.2. 5.2. Surface DCGLs for Non-Activated Areas The RESRAD-BUILD code was run using default parameters to determine surface DCGLs corresponding to the 25 mrem/yr year limit. The output reports are provided in Attachment 3 of this Plan. These surface DCGLs correspond to total contamination (fixed and removable). The default model assumes that 10% of the contamination is removable; consequently, a removable activity limit equal to 10% of the surface DCGL is implemented to confirm this important assumption. Table 5-3 shows the radionuclide specific surface DCGLs for this project.
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Table 5-3: DCGLsurface for Nuclides of Concern at 25 mrem/yr
Radionuclide DCGL
(dpm/100cm2)
Removable Activity Limit
(dpm/100cm2)
Ag-108m 2.8E+04 2.8E+03
Ag-110m 3.0E+04 3.0E+03
Cd-109 5.2E+05 5.2E+04
Co-56 7.4E+04 7.4E+03
Co-57 6.6E+05 6.6E+04
Co-58 2.0E+06 2.0E+05
Co-60 2.1E+04 2.1E+03
Cr-51 1.3E+07 1.3E+06
Cs-134 3.6E+04 3.6E+03
Eu-152 4.0E+04 4.0E+03
Eu-154 3.7E+04 3.7E+03
Eu-155 5.7E+05 5.7E+04
Fe-55 2.0E+07 2.0E+06
Fe-59 3.0E+06 3.0E+05
H-3 2.4E+08 2.4E+07
Mn-54 9.1E+04 9.1E+03
Na-22 2.7E+04 2.7E+03
Nb-95 6.8E+05 6.8E+04
Sb-124 1.7E+06 1.7E+05
Sc-46 1.6E+07 1.6E+06
Zn-65 1.4E+05 1.4E+04
The field instruments used to collect survey data are not equipped to distinguish between radionuclides. The measurements are analyzed for gross beta/gamma only. Therefore, measurements of surface activity are evaluated against the most limiting surface DCGL which is Co-60 at 21,000 dpm/100cm2 total activity. The removable activity measurements will be evaluated against 10% of the surface activity limit (i.e., 2,100 dpm/100cm2). 6. PLANNED DECOMMISSIONING ACTIVITIES This section describes the work activities that are necessary to accomplish decommissioning. Because all work will be conducted by Ameriphysics in accordance with Ameriphysics’ Radiological Control Procedure Manual, a detailed discussion of these activities is not provided unless otherwise specified.
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6.1. Characterization The extent to which the cyclotron room is impacted by long-lived radionuclides is typically evaluated following cyclotron removal. To aid in development of remediation planning and development of this Plan, a shielded 2-inch x 2-inch (2” x 2”) sodium iodide (NaI) detector was used to assess the site prior to removal of the cyclotron. Core samples were also performed to access the radionuclides of concern and the depth of activation in the concrete vault structure. A NaI background value of 3,527 cpm was determined by calculating the average of several one-minute static measurements from concrete surfaces outside of the cyclotron vault. A NaI scan survey was then performed inside the vault. It was immediately evident during the scan survey that the cyclotron and other components remaining in the room were significantly affecting background. However, the walls and floor nearest the cyclotron target assembly exhibited significantly higher count rates. So characterization was limited but somewhat possible using the NaI detector. Following NaI scan surveys, NaI detector one-minute static measurements were performed at multiple locations. The results of the one-minute NaI readings are provided in Figure 6-1.
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Figure 6-1: Radiological Investigation Areas
Core sampling was performed at five locations. These locations were chosen based on the NaI results and accessibility. The south wall was inaccessible so it was not sampled. The samples were analyzed off site via gamma spectroscopy by GEL Laboratories in Charleston, SC. The laboratory results are attached in their entirety in Attachment 1 and are summarized in
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Table 6-1.
Table 6-1: Summary of Cyclotron Room Sample Results
Nuclide
Sample Results (pCi/g)
Cyclotron Vault
Floor (0-6 inch)
Cyclotron Vault
Floor (6-15 inch)
Cyclotron Vault East Wall (0-6
inch)
Cyclotron Vault
West Wall (0-6 inch)
Cyclotron Vault
North Wall (0-6 inch)
Cyclotron Vault
Hallway (0-9 inch)
Antimony-124 ND ND ND ND ND ND
Cadmium-109 ND ND ND ND ND ND
Cesium-134 1.94 0.415 1.60 0.594 1.36 0.668
Chromium-51 ND ND ND ND ND ND
Cobalt-56 ND ND ND ND ND ND
Cobalt-57 ND ND ND ND ND ND
Cobalt-58 ND ND ND ND ND ND
Cobalt-60 15.9 3.93 9.95 4.26 7.94 3.93
Europium-152 43.2 11.6 26.4 11.2 24.0 13.7
Europium-154 4.41 0.959 3.43 1.16 2.52 1.31
Europium-155 ND ND ND ND ND ND
Iron-59 ND ND ND ND ND ND
Manganese-54 1.26 ND 2.44 ND 1.29 0.294
Niobium-95 ND ND ND ND ND ND
Scandium-46 0.792 0.249 0.673 0.294 0.564 0.258
Silver-108m ND ND ND ND ND ND
Silver-110m ND ND ND ND ND ND
Sodium-22 ND ND ND ND ND ND
Zinc-65 1.03 ND 2.25 1.04 2.19 0.851
Total Activity: 68.5 17.2 46.7 18.6 39.9 21.0
ND = Not Detected Following the characterization activities, additional information was located which indicated that additional radionuclides of concern (H-3 and Fe-55) were likely to be present at relatively low concentrations compared to their DCGLs. Following the removal of the cyclotron, additional samples were collected for H-3 and Fe-55 analysis. The analytical results did indicate the presence of these radionuclides. Tritium was detected up to 80.1 pCi/g and Fe-55 up to 358 pCi/g.
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6.2. Remediation Based on the characterization described in the previous section and Ameriphysics’ experience on similar projects, remediation is expected to be limited to approximately two feet of concrete and steel of the inner vault areas. Remediation of the vault will be performed using a hydraulic excavator with a hammer attachment and various handheld tools (e.g., chipping hammers, reciprocating saws, etc.). No decontamination of any other areas outside the vault is anticipated. Although the concrete within the vault is expected to be activated to a depth of approximately two feet, the entire vault will be removed as part of the project. An opening will be made on the north side of the building to allow access to the vault’s exterior north wall. Temporary doors will be installed at the opening to control access to the restricted area. Using the excavator, demolition of the vault will begin with the exterior of the north wall. This wall is approximately 5.5 feet thick. Since the wall is expected to be activated on the interior 2 feet, most of the concrete rubble created initially is expected to be clean (non-activated). This rubble/debris will be segregated and surveyed for free release (See section 6.4). Once the concrete is removed to the point of activation, all rubble will be managed as radioactive waste. Following the removal of the north wall, the opening will allow access to the interior of the vault. The interior walls and ceiling surfaces will be remediated until the activated concrete has been removed. The remaining wall and ceiling surfaces will be demolished and the rubble/debris will be surveyed for free release. After removal of the walls and ceiling, the activated floor concrete will be remediated. A final status survey of the remaining floor surfaces will be performed as described in Section 12. Because of the relatively small footprint of the facility, space is very limited for the demolition activities. Enclosures (e.g., temporary containment tents with HEPA filtration units) will be utilized, as necessary, to ensure that contamination is controlled and no releases to the public occur. 6.3. Air Sampling and Concrete Dust Control Air sampling will be performed during potential airborne radioactivity producing activities (i.e., activated concrete demolition). The sampling will include breathing zone, general area, and effluent sampling, as appropriate. If air samples indicate the presence of airborne radioactivity above 1 Derived Air Concentration (DAC) within the work area, work will be stopped and additional radiological controls will be implemented (e.g., additional misting, slower demolition, additional HEPA ventilation).
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If necessary, a temporary containment tent with local HEPA filtration will be constructed adjacent to the cyclotron vault on the exterior of the building to extend the work area. All radiological remediation operations will be performed within the building or within containment areas (other than final waste package loading on the transport vehicle). Misting and/or air filtration will be used to control dusts as necessary. Continuous air sampling will be performed outside the restricted area for effluent monitoring. These samples will be evaluated against the most restrictive radionuclide of concern (Eu-154 effluent limit = 3E-11 µCi/ml). 6.4. Survey and Removal of Clean Concrete Debris Clean concrete debris will be generated as a result of vault decommissioning activities. The concrete debris will be scan surveyed using a pancake GM detector and a 2” x 2” NaI detector using the typical operating parameters identified in Table 9-3. If no activity exceeding minimum detectable concentrations (MDC) from Table 9-3 is detected, the material will be placed in a segregated roll-off container for disposal/recycle as clean material. Removable contamination measurements will be performed during the process and analyzed using a Ludlum 3030E (or equivalent) dual alpha/beta wipe sample counter. The surveys will be documented and reviewed prior to release of the debris for disposal/recycle.
7. PROJECT MANAGEMENT AND ORGANIZATION The specific responsibilities and authority of management, safety and health, and other personnel on this site are detailed in the following paragraphs. One person may fill more than one role. 7.1. Project Manager (PM) The PM has responsibility and authority to direct all work operations. The PM coordinates safety and health functions, has the authority to oversee and monitor the performance of the Plan, and bears ultimate responsibility for the proper implementation of this Plan. The specific duties of the PM are:
• Managing the project and overseeing the technical and programmatic activities of the health and safety program;
• Ensuring that adequate health and safety systems (policies, plans, procedures, materials, etc.) are in place and operational;
• Assigning sufficient resources to maintain and implement the health and safety program;
• Ensuring effective emergency response;
• Serving as primary site liaison with public agencies and officials and site contractors;
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• Managing the safety and health functions on this site;
• Serving as the site’s point of contact for safety and health matters;
• Ensuring site monitoring, worker training, medical surveillance, and effective selection and use of personal protective equipment (PPE);
• Ensure the correct field execution of the Plan;
• Assessing site conditions for unsafe acts and conditions and providing corrective action;
• Maintaining effective safety and health records as described in this Plan; and
• Coordinating with the emergency response personnel and others as necessary for safety and health efforts.
7.2. Field Personnel Field personnel are responsible for complying with this Plan and other written work documents, using the proper PPE, reporting unsafe acts and conditions, and following the lines of authority established for this project site. Other, general responsibilities of all project personnel include:
• Maintaining complete, factual, detailed, and objective records;
• Safeguarding record materials, including, but not limited to, field notebooks, raw data sheets, and chain-of-custody forms;
• Taking all reasonable precautions to prevent injury to themselves and to their fellow employees;
• Being alert to potentially harmful situations;
• Performing only those tasks that they believe they can do safely and immediately reporting any accidents and/or unsafe conditions to the PM;
• Notifying the PM of any special medical conditions (i.e., allergies, contact lenses, diabetes, and medication use);
• Preventing spillage to the extent possible, and in the event spillage occurs, containing the spillage and notifying the PM (note: field personnel should not engage in spill containment or cleanup if conditions are not safe and if the cleanup cannot be accomplished with supplies available at the site);
• Avoiding splashing materials to the extent possible;
• Practicing good housekeeping by keeping the work area neat, clean, and orderly to the extent possible;
• Reporting all injuries - no matter how minor; and
• Ensuring that proper waste management procedures are followed.
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7.3. Coordination of Efforts The other contractors and subcontractors on this site who could be affected by the tasks and operations associated with the Plan are listed in Table 7-1 below.
Table 7-1: Other Site Contractors and Subcontractors
Company Function
Cardinal Health Client/Site Lessee
Rowe Transfer Prime Contractor
Ameriphysics Sub-Contractor to Rowe Transfer
All work shall be performed by Ameriphysics and Rowe Transfer, as contractors of Cardinal Health, under Ameriphysics’ radioactive material license. The following organizations will be participating to accomplish the work:
• Cardinal Health leases the facility and has contracted Ameriphysics via Rowe Transfer to perform the activities described in this Plan; therefore, Cardinal Health is responsible for ensuring that Ameriphysics fulfills the portion of the work for which they have been contracted. Cardinal Health is responsible for providing site access, removing interferences, identification and marking of utilities, and backfill/restoration.
• Rowe Transfer is the prime contractor that teams with Ameriphysics and is responsible for the cyclotron removal, packaging and loading activities associated with the project.
• Ameriphysics is responsible for collecting the data necessary to support a decision regarding the radiological condition of the facility. Ameriphysics’ PM shall be the person directly responsible for all onsite operations related to the project.
• The NRC is the organization responsible for providing the regulatory authority necessary to perform the work and release the facility. The NRC will provide regulatory oversight, as they determine appropriate, in various areas including health physics, quality assurance, and industrial health and safety. The NCR is responsible for reviewing the data presented by Ameriphysics and making the final decision regarding disposition of the site.
8. HEALTH AND SAFETY PROGRAM DURING DECOMMISSIONING Ameriphysics maintains a comprehensive health and safety program, and specific individual programs, that have been developed to assure compliance with federal, state, and local regulations.
Ameriphysics' Health and Safety Manual will be followed by all who are working under Ameriphysics' license for the duration of the project.
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9. SURVEY INSTRUMENTATION Based on potential contaminants, their associated radiations, and the types of residual contamination categories to be evaluated, the detection sensitivities of various instruments and techniques were evaluated for use. Instruments are evaluated for use during surface scans, direct measurements, and analysis of removable contamination wipes. 9.1. Instrument Calibration Laboratory and portable field instruments are calibrated at least annually with National Institute of Standards and Technology (NIST) traceable sources and to radiation emission types and energies that provide detection capabilities similar to the nuclides of concern. 9.2. Daily Response Checks For radiological instruments operated by Ameriphysics, a reference source is measured prior to use each day. The result is accurate if it falls within ±20% of originally determined values. This is consistent with the guidance in Section 6.5.4 of MARSSIM, Instrument Calibration. Background readings are taken as part of the daily response checks and compared with the acceptance range for instrument and site conditions determined during instrument set up in accordance with Ameriphysics Survey Instrument Procedure, RCP 4-3. If an instrument fails a response check, all data obtained with the instrument since the last satisfactory check is invalidated. 9.3. Determination of Counting Times and Minimum Detectable Concentrations Minimum counting times for background determinations and counting times for measurement of total and removable contamination are chosen to provide MDCs that meet the Data Quality Objectives (DQOs) specified in this Plan. MARSSIM equations relative to building surfaces are modified to convert to units of dpm/100 cm2. Count times and scanning rates are determined using the equations in the following sections. 9.3.1. Static Counting Static counting MDC at a 95% confidence level is calculated using the following equation, which is an expansion of NUREG-1507, “Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions”, Table 3.1 (Strom & Stansbury, 1992):
2100
)1(29.33
cm
AET
T
TTR
MDC
totalBS
B
BSBSB
static
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Where: MDCstatic = minimum detectable concentration level in dpm/100cm2 RB = background count rate in counts per minute (cpm) TS+B = sample count time in minutes TB = background count time in minutes Etotal = total detector efficiency for radionuclide emission of interest
(includes combination of the 2π instrument efficiency and surface efficiency)1
A = detector area in cm2 1. Surface efficiency applied will be in accordance with the recommended value of 0.25 for beta emitters <400keV
EMAX.
9.3.2. Ratemeter Scanning Scanning MDC at a 95% confidence level is calculated using the following equation which is a combination of MARSSIM equations 6-8, 6-9, and 6-10:
2100
60'
cm
AEp
ibd
MDC
tot
i
scan
Where: MDCscan = minimum detectable concentration level in dpm/100 cm2 d’ = desired performance variable (1.38) bi = background counts during the residence interval i = residence interval p = surveyor efficiency (0.5) Etot = total detector efficiency for radionuclide emission of interest
(includes combination of the instrument 2π efficiency and surface efficiency1)
A = detector probe area in cm2
1. Surface efficiency applied will be in accordance with the recommended value of 0.25 for beta emitters <400 keV EMAX.
9.3.3. Gamma Scans Surface scans are conducted with a shielded 2” x 2” NaI detector for each potentially volumetrically activated survey unit. The scan survey coverage requirements are discussed further in Section 12.4. Gamma scans will be conducted with a Ludlum 2221 survey instrument coupled to a Ludlum 44-10 NaI detector, or equivalent.
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The MDC for scans used to evaluate volumetric activity against the DCGLs is determined using the approach presented in Section 6 of NUREG-1507, “Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions”. Using this approach, the relationship between the surveyor minimum detectable count rate (MDCsurveyor) and the radionuclide concentration is determined in two steps. First, the relationship between the radionuclide concentration and exposure rate is determined; second, the relationship between the detector’s net count rate to net exposure rate (cpm per μR/h) is established. The method requires modeling (using MicroShield) of a small area of elevated activity as a cylindrical volume to determine the net exposure rate. The measurements will be taken at the average height of the NaI scintillation detector above the source during scanning. A model that conservatively estimates MDCsurveyor was developed. The following input parameters were used:
Areal dimension of the cylindrical hot spot: 0.25 m2 (radius of 28 cm) Depth of hot spot: 15 cm Dose point: 10 cm above surface Density of hot spot: 2.35 g/cm3
Note that this model reflects the exact conditions of the methodology presented in NUREG-1507, with the exception of density. In this instance, the MicroShield default density for concrete was used rather than soil. While DCGL development was based on activation in the first 30 cm of building material, a hot spot depth of 15 cm was determined to be appropriate for MDC calculation because it reflects the reasonable detection capabilities of the NaI detector. Nuclide activities were calculated by multiplying the activity concentrations of the highest sample by the mass of the modeled volume (86,777 grams). The modeling code performed the appropriate calculations and determined the total exposure rate, 50.4 μrem/hr, which accounts for buildup. The dose modeling report from MicroShield is included as Attachment 4. Additionally, Microshield provided the exposure rate for a number of gamma energies associated with the input source term. These data were used along with data for a 2” x 2” NaI detector from NUREG-1507, Table 6.3, to weight the cpm/μrem/hr value at each energy by the fractional exposure rate to estimate an overall cpm/μrem/hr value specific to the source term.
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Table 9-1: Weighted cpm/μrem/hr for 2” x 2” NaI
Energy (keV) Exposure
Rate (μrem/hr)
Exposure Rate Fraction
cpm/μrem/hr1
cpm/μrem/hr (weighted)
152 1.43E-02 2.83E-04 2.20E+03 6.22E-01
30 4.40E-05 8.73E-07 5.16E+03 4.51E-03
40 1.39E-01 2.75E-03 8.88E+03 2.44E+01
50 4.77E-02 9.45E-04 1.18E+04 1.12E+01
100 4.02E-01 7.98E-03 9.84E+03 7.85E+01
200 3.18E-01 6.31E-03 4.23E+03 2.67E+01
300 1.77E+00 3.51E-02 2.52E+03 8.85E+01
400 5.79E-01 1.15E-02 1.70E+03 1.95E+01
500 8.34E-02 1.65E-03 1.27E+03 2.10E+00
600 1.46E+00 2.90E-02 1.01E+03 2.93E+01
800 5.64E+00 1.12E-01 7.10E+02 7.94E+01
1000 1.94E+01 3.85E-01 5.40E+02 2.08E+02
1500 2.05E+01 4.07E-01 3.50E+02 1.43E+02
2000 8.90E-08 1.76E-09 2.60E+02 4.59E-07
Total: 5.04E+01 Total Weighted
cpm/μrem/hr: 7.11E+02
1 Values from NUREG-1507 Table 6.3. 2No value listed on table for 15 keV. The value for 20 keV used.
The scan MDC for a 2” x 2” NaI detector was calculated using the following inputs:
Scan rate of 0.5 meters per second provides an observation interval of approximately 1 second based on a hot spot diameter of 56 cm
Locally determined background is expected to be less than or equal to 3,527 cpm The desired level of surveyor performance, 95% correct detections and 60% false positive
rate, results in a d’ of 1.38 The surveyor efficiency (p) is assumed to be 0.5
Based on these inputs, MDCRsurveyor was calculated as follows: 1) Bi = (3,527 cpm) * (1 sec) * (1min/60 sec) = 58.78 counts 2) MDCR = (1.38) * sqrt(58.78) * (60 sec/1 min) = 635 cpm 3) MDCRsurveyor = 635 cpm/sqrt(0.5) = 898 cpm The corresponding Minimum Detectable Exposure Rate is determined by dividing the MDCRsurveyor by the weighted conversion factor determined in Table 9-1 (equation 6-18 of NUREG-1507): Minimum Detectable Exposure Rate = 898 cpm / 711 cpm/μrem/hr = 1.26 μrem/hr
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Finally, the radionuclide concentrations necessary to yield the minimum detectable exposure rate was calculated using equation 6-22 of NUREG-1507 as follows: Scan MDC = (68.5 pCi/g) * 1.26 μrem/hr / 50.4 μrem/hr = 1.71 pCi/g The MDC of the scan procedure – needed to detect an area of elevated activity at the limit determined by the area factor – is discussed in Section 5.5.2.4 of MARSSIM and calculated as follows: Scan MDC (required) = DCGL x Area Factor Areas smaller than the area for which the DCGL is calculated result in area factors greater than one. Because the most restrictive DCGL is 5.41 pCi/g (Co-60) and the Scan MDC is well less than 50% of this value, we can conclude that the Scan MDC is appropriate without calculating area factors. 9.3.4. Removable Contamination Measurement Counting Removable contamination measurement (smear) counting Minimum Detectable Concentration at a 95% confidence level is calculated using the following equation, which is NUREG-1507, “Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions”, Table 3.1 (Strom & Stansbury, 1992):
Et
t
ttB
MDCs
b
ssr
smear
)1(29.33
Where: MDCsmear = minimum detectable concentration level in dpm/smear Br = background count rate in counts per minute tb = background count time in minutes ts = sample count time in minutes E = 4π instrument efficiency for radionuclide emission of interest
9.4. Counting Uncertainty The counting uncertainty for both total and removable measurements is calculated using equation 6-15 from MARSSIM:
2 2
s b bR
s b b
C C
T T
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Where: σR = uncertainty Cs+b = gross counts of the sample Ts+b = Sample time (minutes) Cb = Gross background counts Tb = Background count time (minutes) 9.5. Instrumentation Specifications The instrumentation to be used for facility decommissioning surveys is summarized in the following tables. Table 9-2 lists the standard features of each instrument such as probe size and efficiency. Table 9-3 lists the typical operational parameters such as scan rate, count time, and the associated MDCs. Alternate or additional instrumentation with similar detection capabilities may be utilized as needed for survey requirements with the Ameriphysics’ Project Manager approval.
Table 9-2: Instrumentation Specifications
Detector Model
Detector Type Detector
Area Meter Model
Window Thickness
Typical Total Efficiency
Ludlum 43-93 Alpha/Beta Scintillation
100 cm2 Ludlum
2360 0.8
mg/cm2 8 % (99Tc) – Beta
Ludlum 43-10-1
Alpha/Beta Scintillation
100 cm2 Ludlum
3030 0.4
mg/cm2 18% – Beta
Ludlum 43-37 Alpha/Beta
Gas Proportional
584 cm2 Ludlum
2360 0.8
mg/cm2 8 % (99Tc) – Beta
Ludlum 44-10 Gamma
Scintillation 2” x 2”
NaI Ludlum
2221 N/A 640 cpm/uR/hr
Table 9-3: Typical Instrument Operating Parameters and Sensitivities
Measurement Type
Detector Model
Meter Model
Scan Rate
Count Time
Background
(cpm) MDC
(dpm/100cm2)1
Surface Scans 43-93 Ludlum
2360 3
cm/sec. N/A 400 2,442 – Beta
Total Surface Activity
43-93 Ludlum
2360 N/A
60 sec.
400 1,201 – Beta
Surface Scans 43-37 Ludlum
2360 3
cm/sec. N/A 700 859 – Beta
Gamma Scans 44-10 Ludlum
2221 0.5
m/sec. N/A 2,577 1.71 pCi/g
Removable Beta Activity
Ludlum 43-10-1
Ludlum 3030E
N/A 60
sec. 70 – Beta 223 – Beta
Note 1: Unless otherwise specified.
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9.6. Background Determination For surveys in areas that were not exposed to a neutron flux, gross beta/gamma total surface activity measurements are performed. The use of reference background areas or paired background comparisons is not necessary for the purposes of this Plan since the radionuclides of concern do not exist in background or they exist at very small fractions of the DCGLs. An ambient background measurement taken at waist level in the center of each survey unit will be used. The ambient background value will be subtracted from the applicable gross measurement count rates (in cpm) to determine the net measurement count rate. For areas that were exposed to a neutron flux (e.g., Cyclotron Room), 10 cm readings using a shielded 2” x 2” NaI detector will be collected on concrete surfaces outside the Cyclotron Room. 10. RADIOACTIVE WASTE MANAGEMENT PROGRAM Radioactive wastes generated as a result of decontamination will be transported to either a licensed radioactive materials processor or for direct disposal at a licensed radioactive materials disposal facility. 10.1. Waste Characterization Previously obtained sample results will be used to develop an "assayed" source representative of the mix of nuclides in the waste. Activities of the concrete wastes may be estimated using the sample results collected during the characterization multiplied by the weight of the wastes. The absolute amount is not required; only the relative quantities, in terms of total activity. If radioactive wastes exceeding the expected values from Table 5-1 are identified, waste material may be characterized using the MicroShield Infer Source tool in terms of radionuclide identification, total activity, and specific activity. 10.2. Waste Shipment Waste containers will be prepared, loaded, and manifested by personnel who have satisfied the training requirements of Title 49 of the Code of Federal Regulations (CFR) Part 172, Subpart H. Shipping papers will reflect Cardinal Health as the generator. 11. QUALITY ASSURANCE PROGRAM
Ameriphysics' Quality Assurance Program comprises the planned and systematic actions
necessary to provide adequate confidence that a system, component, or service achieves a level
of quality which meets or exceeds established requirements.
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In addition to the Ameriphysics Quality Assurance Program, a project specific Quality Assurance Project Plan (QAPP) will be prepared that presents the organization, objectives, functional activities, and specific quality assurance (QA), and quality control (QC) activities associated with the decommissioning of the cyclotron facility, in St Louis, Missouri. The QAPP will describe the specific protocols that will be followed for field measurements, instrument control and calibration, sampling, sample handling and storage, chain of custody, and laboratory analysis. The plan will present details regarding data quality objectives (DQOs) for the project, field and sample documentation, sample packaging and shipping, and laboratory analytical procedures. Ameriphysics will submit a project-specific Quality Assurance Project Plan (QAPP) utilizing the guidelines of MARSSIM Section 9. The QAPP will be reviewed and approved by Cardinal Health prior to commencing decommissioning. The QAPP will incorporate at a minimum, the following sections:
• Introduction
• Project Organization and Responsibilities
• On Site Organization for Measurements and Laboratory Analysis
o Subcontract Support
• Data Quality Objectives
o Specific Data Quality Objectives
• QC Measurements, Samples, Holding Times, Custody
o QC Measurements and Samples
o Chain of Custody (COC)
o Off Site Laboratory Custody Procedures
o Sample Numbering and Field Documentation
• Procedures
• On Site Laboratory and Field Instruments
• Calibration Procedures and Frequency
• Internal Quality Control Checks
o Instrument QC
o QC Samples
• Calculation of Data Quality Indicators
o Field Measurement Data
o Laboratory Data
• Corrective Actions
• Data Reduction, Validation, and Reporting
o Field Measurements and Sample Collection
o Contract Laboratory Services
o On Site Laboratory Results
o Data Validation
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• Preventative Maintenance Procedures
o Field Instruments and Equipment
o Laboratory Instruments
• Performance and System Audits
12. FACILITY RADIATION SURVEYS Final status surveys are performed to demonstrate that residual radioactivity in each survey unit satisfies the predetermined criteria for release for unrestricted use. The final status survey is designed using the DQO process. Final status surveys are conducted by performing required scan surveys, total direct surveys, and removable contamination measurements. All survey data is documented on survey maps and associated data information sheets. 12.1. Data Quality Objectives The process of designing a final status survey begins with development of DQOs. On the basis of these objectives and the known or anticipated radiological conditions at the site, the numbers and locations of measurement and sampling points used to demonstrate compliance with the release criterion are then determined. Finally, survey techniques appropriate to develop adequate data are selected and implemented. Survey results obtained in accordance with the MARSSIM guidelines are used to select between one condition of the environment (the null hypothesis, H0) and an alternative condition (the alternative hypothesis, Ha). The null hypothesis is treated like a baseline condition that is assumed to be true in the absence of strong evidence to the contrary. Acceptance or rejection of the null hypothesis depends upon whether or not the particular survey results are consistent with the hypothesis. A decision error occurs when the decision maker rejects the null hypothesis when it is true, or accepts the null hypothesis when it is false. These two types of decision errors are classified as Type I and Type II decision errors. A Type I decision error occurs when the null hypothesis is rejected when it is true, and is sometimes referred to as a false positive error. The probability of making a Type I decision error, or the level of significance, is denoted by alpha (α). Alpha reflects the amount of evidence the decision maker would like to see before abandoning the null hypothesis, and is also referred to as the size of the test. A Type II decision error occurs when the null hypothesis is accepted when it is false. This is sometimes referred to as a false negative error. The probability of making a Type II decision error
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is denoted by beta (β). The term (1- β) is the probability of rejecting the null hypothesis when it is false, and is also referred to as the power of the test. The null hypothesis for this project is that the residual radioactivity concentrations exceed the release criterion. Acceptable decision error probabilities for testing the hypothesis are set at α = 0.05 and β = 0.05. 12.2. Area Classification Classification is a critical step in the survey design process. Areas that have no reasonable potential for residual contamination do not need any level of survey coverage and are designated as non-impacted areas. These areas have no radiological impact from site operations. Impacted areas are areas that have some potential for containing residual radioactivity. They are subdivided into the following three classes:
• Class 1 areas: Areas that have, or had prior to remediation, a potential for radioactive contamination or known contamination. Examples of Class 1 areas include site areas previously subjected to remedial actions, locations where leaks or spills are known to have occurred, former burial or disposal sites, waste storage sites, and areas with contaminants in discrete solid pieces of material high specific activity.
• Class 2 areas: These areas have, or had prior to remediation, a potential for radioactive contamination or known contamination, but are not expected to exceed the DCGL. To justify changing an area's classification from Class 1 to Class 2, the existing data (from the historical site assessment, scoping surveys, or characterization surveys) should provide a high degree of confidence that no individual measurement would exceed the DCGL. Examples of areas that might be classified as Class 2 include locations where radioactive materials were present in an unsealed form, potentially contaminated transport routes, upper walls and ceilings of rooms subjected to airborne radioactivity, areas where low concentrations of radioactive materials were handled, and areas on the perimeter of former contamination control areas.
• Class 3 areas: Any impacted areas that are not expected to contain any residual radioactivity, or are expected to contain levels of residual radioactivity at a small fraction of the DCGL, based on site operating history and previous radiological surveys. Examples of areas that might be classified as Class 3 include buffer zones around Class 1 or Class 2 areas, and areas with very low potential for residual contamination but insufficient information to justify a non-impacted classification.
The working hypothesis of MARSSIM is that all impacted areas being evaluated for release have a potential for radioactive contamination above the DCGL. This initial assumption means that all areas are initially considered Class 1 areas unless some basis for reclassification as Class 2, Class 3 or non-impacted is provided. Consistent with this approach, Class 1 areas have the greatest
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potential for contamination and, therefore, receive the highest degree of survey effort, followed by Class 2 and then Class 3 areas. For the purposes of this Plan, the floors of the restricted area are classified as Class 1. The lower walls and support spaces making up the balance of the restricted area are classified as Class 2. The upper walls and ceilings of these spaces are classified as non-impacted unless during scan surveys of the lower walls, there is an indication that further investigation of the upper walls and ceilings is warranted. The floors in the non-restricted areas are classified as Class 3. 12.3. Survey Unit Identification A survey unit is a physical area consisting of structures or land areas of specified size and shape for which a separate decision is made as to whether or not that area exceeds the release criterion. As this decision is made as a result of the final status survey, the survey unit is the primary entity for demonstrating compliance with the release criterion. To facilitate survey design and ensure that the number of survey data points for a specific site is relatively uniformly distributed among areas of similar contamination potential, the site is divided into survey units that share a common history or other characteristics, or are naturally distinguishable from other portions of the site. A survey unit should not include areas that have different classifications. The survey unit’s characteristics should be generally consistent with exposure pathway modeling that is used to convert dose or risk into radionuclide concentrations. For indoor areas each room may be designated as a survey unit. Indoor areas may also be subdivided into several survey units of different classification, such as separating floors and lower walls from upper walls and ceilings (and other upper horizontal surfaces) or subdividing a large warehouse based on floor area. MARSSIM states that survey units should be limited in size based on classification, exposure pathway modeling assumptions, and site-specific conditions. MARSSIM also suggests size limitations, which for Class 1 structural surfaces is 100 m2 or less (floor area) and Class 2 structural surfaces 100 to 1,000 m2. Both Class 1 and Class 2 survey units are less than these size recommendations. MARSSIM does not have a suggested limit for class 3 survey units.
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Initial survey unit classification is as follows:
Table 12-1: Initial Survey Unit Classification
Survey Unit ID
Description Approximate Survey Area
(m2)
Initial Classification
SU 1 Cyclotron Room Floor (walls and ceiling to be removed)
72 Class 1 Impacted
SU 2-4 Restricted Area Floors 51, 99, & 59 Class 1 Impacted
SU 5 Restricted Area Walls (0-2
meters) 350 Class 2 Impacted
SU 6 Non-Restricted Area Floors 155 Class 3 Impacted
12.4. Surface Scans Scanning is used to identify locations within the survey unit that exceed the investigation level, which for this survey is the DCGL. These locations are marked and receive additional investigations to determine the concentration, area, and extent of the contamination. Scanning surveys are designed to detect small areas of elevated activity that are not detected by the measurements using the systematic pattern. For this reason, the measurement locations and the number of total surface activity measurements may need to be adjusted based on the sensitivity of the scanning technique. Scan surveys are performed for gross beta/gamma in all potentially contaminated areas that have no potential for volumetric activation. NaI scans are performed in potentially activated areas such as the remaining Cycloton Room floor. NaI scans are performed to meet the survey residence time of 1-second as discussed in Section 9.3.3. For the purposes of the final status survey, Class 1 survey units will receive a 100% scan survey of all accessible surfaces. Class 2 survey units will receive a minimum of 50% scan survey of all accessible surfaces. Class 3 areas will receive a minimum of 10% scan of all accessible surfaces. If elevated activity is detected during the scan surveys, then the location is marked and samples are taken to quantify the activity. The samples will consist of total and removable surface activity for non-activated areas or concrete samples for activated areas. Note that these measurements are evaluated on an individual basis and are in addition to the static measurements required by MARSSIM. 12.5. Determining the Number of Sample Locations For situations where the contaminant is not present in background, or is present at such a small fraction of the DCGL as to be considered insignificant, a background reference area is not necessary. Instead, the contaminant levels are compared directly with the DCGL value. A one-sample Sign test is used to statistically demonstrate compliance with the release criterion.
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The lower bound of the gray region (LBGR) is selected to be one-half the DCGL and is used as an arbitrary starting point for developing an acceptable survey design along with target values of 0.05 for α and β. The width of the gray region, equal to DCGL minus the LBGR, is a parameter that is central to the Sign test. This parameter is also referred to as the shift, Δ. The absolute size of the shift is actually of less importance than the relative shift, Δ/σ, where σ is an estimate of the standard deviation of the measured values in the survey unit. Values estimated for σ include both the real spatial variability in the quantity being measured and the precision of the chosen measurement system. The relative shift, Δ/σ, is an expression of the resolution of the measurements in units of measurement uncertainty. The importance of choosing appropriate values for σ must be emphasized. If the value is grossly underestimated, the number of data points will be too few to obtain the desired power level for the test and a resurvey may be recommended. Therefore, in the interest of conservatism a larger value is selected even though the number of data points determined is increased. Table 5.5 of MARSSIM provides the number of data points used to demonstrate compliance using the Sign test for selected values of α, β, and Δ/σ. The sample numbers on Table 5.5 of MARSSIM were calculated using the methodology presented in MARSSIM and increased by 20% to account for missing or unusable data. 12.5.1. Number of Gross Beta/Gamma Total Surface Activity Measurements Gross Beta/Gamma measurements consist of static measurements taken with Ludlum 43-93 or equivalent. These measurements will be taken in potentially non-activated contamination areas (areas outside the vault within the restricted area). Since an actual value for σ is not known, it is preliminarily assumed to be no more than 30 percent of the DCGL. This important assumption is confirmed by a post-survey analysis of σ. Using this estimate of σ, the relative shift is calculated using a LBGR of 50 percent of the DCGL (∆ = 1 x DCGL – 0.5 x DCGL). This calculation is shown below.
Relative shift = ∆
𝜎=
1 − 0.5
0.3= 1.6
The value extracted from the table using the expected site-specific parameters is 17 and represents the minimum number of measurements performed in each survey unit. 12.5.2. Number of Volumetric NaI Measurement Locations Volumetric measurements are to be taken with a NaI detector. These measurements are to be taken in potentially activated areas (i.e., footprint of the vault).
1110-PP-001, Rev. 0 August 2016
Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO Page 30 of 35
Since an actual value for σ is not known, it is preliminarily assumed to be no more than 30 percent of the DCGL. This important assumption is confirmed by a post-survey analysis of σ. Using this estimate of σ, the relative shift is calculated using a LBGR of 50 percent of the DCGL (∆ = 1 x DCGL – 0.5 x DCGL). This calculation is shown below.
Relative shift = ∆
𝜎=
1 − 0.5
0.3= 1.6
The value extracted from the table using the expected site-specific parameters is 17 and represents the minimum number of measurements performed in each survey unit. The MDC of the scan procedure – needed to detect an area of elevated activity at the limit determined by the area factor – is discussed in Section 5.5.2.4 of MARSSIM3 and calculated as follows:
Scan MDC (required) = (𝐷𝐶𝐺𝐿𝑊) × (𝐴𝑟𝑒𝑎 𝐹𝑎𝑐𝑡𝑜𝑟) Area factors are determined by taking the ratio of the dose per unit concentration generated by RESRAD-BUILD for the area specified in Section 5.2 to the dose generated by the largest unsampled area. The surface area of the largest area is approximately 72 square meters. When 18 samples are spaced using the procedure specified in section 5.1, the distance between sampling locations is 2 meters. The area encompassed by a square sampling pattern of two meters is four square meters. The actual Scan MDC, 1.71 pCi/g (see Section 9.3.3), is below the most limiting DCGL of 5.41 pCi/g (based on Co-60) which would be much less than a determined elevated measurement (DCGLEMC) for a four square meter unsampled area. As a result, no additional sampling points are necessary for assessment of small areas of elevated activity in the cyclotron activation areas. 12.6. Determination of Sampling Locations Class 1 and Class 2 survey units are sampled using a random start, systematic grid system. After determining the number of samples needed in the survey unit, sample spacing is determined from MARSSIM equation 5-8:
grid squarea for n
AL
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Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO Page 31 of 35
Where: L = sample spacing interval A = the survey unit area n = number of samples needed in the survey unit
Maps are generated of the survey unit’s permanent surfaces included in the statistical tests (floors, walls, ceilings, fixed cabinetry, etc.) and folded out in a 2-dimensional view. A random starting point is determined using computer-generated random numbers coinciding with the x and y coordinates of the total survey unit. A grid is plotted across the survey unit surfaces based on the random start point and the determined sample spacing. A measurement location is plotted at each intersection of the grid plot. In addition to the survey locations identified for statistical evaluations and elevated measurement comparisons, data may be obtained from judgmental locations that are selected due to unusual appearance, location relative to contamination areas, high potential for residual activity, general supplemental information, etc. Data points selected based on professional judgment are not included with the data points from the systematic grid for statistical evaluations; instead they are compared individually with the established DCGLs and conditions. Measurement locations selected based on professional judgment violates the assumption of unbiased measurements used to develop the statistical tests described by MARSSIM. 12.7. Total Surface Activity Measurements Direct surveys (static measurements) are performed on building surfaces to the extent practical in impacted areas utilizing instrumentation of the best geometry based on the surface at the survey location. Additionally, locations of elevated activity identified and marked during the scan survey require total activity measurements. Total surface contamination measurements for gross beta are taken at statistically determined sample locations. Scaler count times are based on achieving detection sensitivity below the DCGL. 12.8. Gamma Radiation Measurements In the potentially activated areas, one-minute static gamma measurements will be collected at each of the determined sample locations using the shielded 2” x 2” NaI detector (see Sections 12.5.2 and 12.6). The measurements will be collected at a similar geometry as the scan surveys (10 cm from the applicable surface). Additional judgmental locations will be collected at any locations exhibiting elevated count rates identified during the scan surveys.
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Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO Page 32 of 35
12.9. Removable Contamination Measurements Removable contamination measurements (smears) are collected on building surfaces and structures at each sample location (surface and activation areas) to determine the potential removable contamination. For each sample, an area of approximately 100 cm2 is wiped. 12.10. Volumetric Core Samples Core-sampling will be performed at each of the determined sample locations in potentially activated areas (see sections 12.5.2 and 12.6). The samples will be obtained to a depth of 15 cm. Sample custody will be maintained at all times. Additional judgmental locations will be collected at locations exhibiting elevated count rates identified during the scan surveys. The samples will be sent to an off-site laboratory for gamma spectroscopy analysis. The laboratory will report the radionuclides identified in Table 4-1 and all other true positive results. Analysis for the hard-to-detect radionuclides (H-3 and Fe-55) will only be performed on 10% of the total number of samples. These will be selected based on the highest 2” x 2” NaI detector readings determined during scan surveys. An average distribution will be determined to ratio the hard-to-detect radionuclides into the sample results for the remaining samples. 12.11. Survey Investigation Levels for Non-Activated Surfaces Investigation levels are used to flag locations that require special attention and further investigation to ensure areas are properly classified and adequate surveys are performed. These locations are marked and receive additional investigations to determine the concentration, area, and extent of the contamination. The survey investigation levels for each type of measurement are listed by classification in Table 12-2.
Table 12-2: Survey Investigation Levels for Non-Activated Surfaces
Survey Unit Classification
Flag Direct Measurement Result When:
Flag Scanning Measurement Result When:
Flag Removable Measurement Result
When:
Class 1 >75% of DCGL >75% of DCGL >1,000 dpm/100cm2
Class 2 >50% of DCGL >50% of DCGL >1,000 dpm/100cm2
Class 3 >10% of DCGL >10% of DCGL >500 dpm/100cm2
12.12. Survey Investigation Levels for Potentially Activated Structures To determine investigation and action levels for activated concrete, some calculations must be performed to correlate the 2” x 2” NaI detector readings in cpm to the activity in pCi/g. The investigation level triggers the need to collect volumetric samples and send for laboratory analysis. The action level triggers the need for additional remediation. The investigation level and the action level are 75% of the DCGLgross and 90% of the DCGLgross, respectively. To determine the
1110-PP-001, Rev. 0 August 2016
Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO Page 33 of 35
corresponding values in cpm for the 2” x 2” NaI detector, the following calculations are performed. The sample results from the 0-6-inch core sample from the cyclotron vault floor had a total activity of 68.5 pCi/g. From the Microshield model, based on this sample, we would have an exposure rate of 50.4 µRem/hr. This results in 0.74 µRem/hr per pCi/g. 50.4 µRem/hr / 68.5 pCi/g = 0.74 µrem/hr per pCi/g We then calculate the expected exposure rate from the surface containing activity at the DCGLgross of 9.41 pCi/g. from Table 5-2. 9.41 pCi/g x 0.74 µrem/hr per pCi/g = 6.96 µrem/hr The cpm value for the 2” x 2” NaI detector that corresponds to the exposure rate of 6.96 µrem/hr is calculated by multiplying by the total weighted cpm/μrem/hr from Table 9-1. 6.96 µrem/hr x 711 cpm/μrem/hr = 4,949 cpm The investigation level at 75% of this value is 3,712 cpm above background. The action level at 90% of this value is 4,454 cpm above bacground. 12.13. Survey Documentation A survey package is developed for each survey unit and may contain the following:
• Survey instruction sheets • General survey requirements • Instrument requirements with associated MDCs, count times and scan rates • Survey maps • Overview maps detailing survey locations and placement methodology • Survey sub-unit maps with additional sample location information, as needed • Survey data sheets • Signature of data collector and reviewer
12.14. Data Validation Field data is reviewed and validated to ensure:
• Completeness of forms and that the type of survey was correctly assigned to the survey unit. • The MDCs for measurements meet the established data quality objectives; independent calculations are performed for a representative sample of data sheets and survey areas.
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Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO Page 34 of 35
• Instrument calibrations and daily functional checks were performed accurately and at the required frequency.
13. EVALUATING SURVEY RESULTS In addition to simply comparing the data against the release criteria, basic statistical quantities are calculated for the data obtained from the survey units. First, the average of the data set and the standard deviation are calculated. The average of the data is compared to the DCGL to get a preliminary indication of the survey unit status. Where remediation is inadequate, this comparison may readily reveal that a survey unit contains excess residual radioactivity - even before applying statistical tests. For example, if every measurement in the survey unit is below the DCGL, the survey unit clearly meets the release criterion. The value of the sample standard deviation is especially important. If the value is too large compared to that assumed during the survey design, this may indicate an insufficient number of samples were collected to achieve the desired power of the statistical test. The median is the middle value of the data set when the number of data points is odd, and is the average of the two middle values when the number of data points is even. Thus 50% of the data points are above the median, and 50% are below the median. Large differences between the average and the median are an early indication of skewness in the data. Ideally, the difference between the average and the mean should be a small fraction of the sample standard deviation. Examining the minimum, maximum, and range of the data may provide additional useful information. The range should not be unusually large. When there are 30 or fewer data points, values of the range much larger than about 4 to 5 standard deviations are considered unusual. For larger data sets the range might be wider. 14. FINAL REPORT A Final Report summarizing decommissioning activities performed at the facility will be prepared and submitted to Cardinal Health for their review and submittal to the NRC. The Final Report will include:
• Introduction
• Radionuclides of Concern
• Facility Description
• FSS Objectives
• FSS Procedures
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Remediation Work Plan, Cardinal Health PET Cyclotron Facility, St Louis, MO Page 35 of 35
• Data Interpretation
• Findings and Results
• Comparison of Results with Guidelines
• Conclusions
Supporting appendices/attachments will also be provided, as required. Discussions therein may include the number of samples and measurements collected, maps and drawings illustrating findings and the locations of samples/measurements, statistical evaluations and other comparisons to guidelines, descriptions of field changes and anomalous results, conclusions based on specific and overall finding of the investigation, and other relevant information as required to demonstrate compliance with this plan and overall project objectives. 15. REFERENCES 1. NUREG-1575, “Multi-Agency Radiation Survey and Site Investigation Manual” (MARSSIM) 2. NUREG-1505, “A Nonparametric Statistical Methodology for the Design and Analysis of Final Decommissioning Surveys" 3. NUREG-1507, “Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions” 4. NUREG-1757, Volume 1 “Consolidated NMSS Decommissioning Guidance,” Appendix B 5. NUREG-1757, Volume 2 “Consolidated NMSS Decommissioning Guidance” 6. ICRP Publication 107, “Nuclear Decay Data for Dosimetric Calculations” 7. 10 CFR 20 Subpart E, “Radiological Criteria for License Termination” 8. Ameriphysics Radiological Control Procedure Manual and associated Procedures. 9. Handbook of Health Physics and Radiological Health, Third Edition.
Attachment 1 Laboratory Sample Analysis Reports for Cyclotron Room Characterization
June 01, 2016 Mr. Paul Jones Ameriphysics, LLC 911 Cross Park Dr. Knoxville, Tennessee 37923 Re: Ameriphysics, LLC Work Order: 398210 Dear Mr. Jones:
GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for thesample(s) we received on May 26, 2016. This original data report has been prepared and reviewed in accordancewith GEL’s standard operating procedures.
Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needson time every time. We trust that you will find everything in order and to your satisfaction. If you have anyquestions, please do not hesitate to call me at (843) 556-8171, ext. 4453.
Sincerely, PM_SIGN_HERE Edith Kent Project Manager
Purchase Order: 0316-001 Enclosures
Page 1 of 24
Kaitlyn Stone for
Reviewed by USER_SIGN_HERE
GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 − (843) 556−8171 − www.gel.com
Certificate of Analysis Report
AMPH002 Ameriphysics, LLC
Client SDG: 398210 GEL Work Order: 398210
Where the analytical method has been performed under NELAP certification, the analysis has met all of therequirements of the NELAC standard unless qualified on the Certificate of Analysis.
The designation ND, if present, appears in the result column when the analyte concentration is not detected abovethe limit as defined in the ’U’ qualifier above.
This data report has been prepared and reviewed in accordance with GEL Laboratories LLCstandard operating procedures. Please direct any questions to your Project Manager, Edith Kent.
The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a Tracer compound** Analyte is a surrogate compoundU Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.UI Gamma Spectroscopy−−Uncertain identification
for
Page 2 of 24
Certificate of Analysis
GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com
Report Date: June 1, 2016
Rad Gamma Spec Analysis
Parameter Result UnitsQualifier Analyst Date Time
15704721126pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g
05/31/16MXR1
DF
Mr. Paul JonesContact:
Ameriphysics, LLCCompany :911 Cross Park Dr.
Knoxville, Tennessee 37923
Address :
Ameriphysics, LLCProject:
398210001Misc Solid19-MAY-16 09:0026-MAY-16
1CVF AMPH002Project:AMPH002Client ID:
Client
+/-0.111+/-2.98
+/-0.220+/-1.06
+/-0.135+/-0.218+/-0.203+/-0.395+/-0.884+/-0.452+/-0.311+/-0.274+/-0.236+/-0.127+/-0.241+/-0.083+/-0.202+/-0.159+/-0.432
Sample ID:
Receive Date:
Client Sample ID:
Matrix:Collect Date:
Collector:
Batch
0.1873.69
0.2301.63
0.2310.4390.2210.1170.4680.4150.5660.4710.2090.2250.2430.1420.3060.3140.465
The following Prep Methods were performed:
Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1
Method Description Analyst Date Time Prep Batch
Method
The following Analytical Methods were performed:
1Method Description
1
DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments
UU
UU
UIU
UU
U
UU
UI
Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65
Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"
Uncertainty
0.03461.071.94
-0.637-0.0918
0.000.0309
15.943.24.41
0.3080.0514
1.260.0400.792
-0.07430.0465
0.001.03
RLMDC
Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).
Page 3 of 24
Certificate of Analysis
GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com
Report Date: June 1, 2016
Rad Gamma Spec Analysis
Parameter Result UnitsQualifier Analyst Date Time
15704721126pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g
05/31/16MXR1
DF
Mr. Paul JonesContact:
Ameriphysics, LLCCompany :911 Cross Park Dr.
Knoxville, Tennessee 37923
Address :
Ameriphysics, LLCProject:
398210002Misc Solid19-MAY-16 09:1026-MAY-16
6CVF AMPH002Project:AMPH002Client ID:
Client
+/-0.062+/-0.895
+/-0.0998+/-0.400
+/-0.0607+/-0.140
+/-0.0543+/-0.152+/-0.385+/-0.207+/-0.131+/-0.111
+/-0.0578+/-0.0521
+/-0.109+/-0.0342+/-0.0841+/-0.0966
+/-0.172
Sample ID:
Receive Date:
Client Sample ID:
Matrix:Collect Date:
Collector:
Batch
0.09911.61
0.09580.7070.0940.186
0.09640.0492
0.2080.3240.2420.186
0.08450.09360.09930.0605
0.1290.0619
0.374
The following Prep Methods were performed:
Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1
Method Description Analyst Date Time Prep Batch
Method
The following Analytical Methods were performed:
1Method Description
1
DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments
UU
UU
UIU
UUUU
UUU
UI
Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65
Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"
Uncertainty
0.00250.4340.4150.152
0.01170.00
0.04323.9311.6
0.9590.0976
-0.04060.07490.0488
0.249-0.00902
0.01670.0356
0.00
RLMDC
Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).
Page 4 of 24
Certificate of Analysis
GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com
Report Date: June 1, 2016
Rad Gamma Spec Analysis
Parameter Result UnitsQualifier Analyst Date Time
15704721127pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g
05/31/16MXR1
DF
Mr. Paul JonesContact:
Ameriphysics, LLCCompany :911 Cross Park Dr.
Knoxville, Tennessee 37923
Address :
Ameriphysics, LLCProject:
398210003Misc Solid19-MAY-16 09:3026-MAY-16
2CVEW AMPH002Project:AMPH002Client ID:
Client
+/-0.0756+/-2.33
+/-0.190+/-0.781
+/-0.0923+/-0.298+/-0.108+/-0.239+/-0.553+/-0.323+/-0.226+/-0.235+/-0.159
+/-0.0856+/-0.148
+/-0.0568+/-0.151+/-0.176+/-0.326
Sample ID:
Receive Date:
Client Sample ID:
Matrix:Collect Date:
Collector:
Batch
0.1392.55
0.1481.18
0.1580.0935
0.1530.0783
0.3280.5730.4110.3180.1460.1550.168
0.09940.228
0.09240.302
The following Prep Methods were performed:
Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1
Method Description Analyst Date Time Prep Batch
Method
The following Analytical Methods were performed:
1Method Description
1
DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments
UU
UU
UIU
UU
UI
UU
UI
Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65
Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"
Uncertainty
0.02420.980
1.600.0317
-0.01690.00
0.03019.9526.43.43
0.104-0.00141
2.440.00
0.6730.0213
0.1990.002.25
RLMDC
Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).
Page 5 of 24
Certificate of Analysis
GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com
Report Date: June 1, 2016
Rad Gamma Spec Analysis
Parameter Result UnitsQualifier Analyst Date Time
15704721138pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g
05/31/16MXR1
DF
Mr. Paul JonesContact:
Ameriphysics, LLCCompany :911 Cross Park Dr.
Knoxville, Tennessee 37923
Address :
Ameriphysics, LLCProject:
398210004Misc Solid19-MAY-16 11:3026-MAY-16
3CVWW AMPH002Project:AMPH002Client ID:
Client
+/-0.0829+/-1.33
+/-0.142+/-0.565
+/-0.0854+/-0.182
+/-0.0942+/-0.218+/-0.483+/-0.259+/-0.180+/-0.174
+/-0.0997+/-0.0815
+/-0.135+/-0.0479
+/-0.118+/-0.125+/-0.275
Sample ID:
Receive Date:
Client Sample ID:
Matrix:Collect Date:
Collector:
Batch
0.1682.12
0.1430.9990.1470.2350.143
0.09260.2820.4930.3100.3090.1250.1430.151
0.08880.192
0.09170.321
The following Prep Methods were performed:
Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1
Method Description Analyst Date Time Prep Batch
Method
The following Analytical Methods were performed:
1Method Description
1
DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments
UU
UU
UIU
UUUU
UUU
Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65
Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"
Uncertainty
0.0300.6290.5940.119
0.005750.00
0.04634.2611.21.16
-0.09170.168
0.08710.0182
0.2940.02520.09090.0317
1.04
RLMDC
Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).
Page 6 of 24
Certificate of Analysis
GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com
Report Date: June 1, 2016
Rad Gamma Spec Analysis
Parameter Result UnitsQualifier Analyst Date Time
15704721139pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g
05/31/16MXR1
DF
Mr. Paul JonesContact:
Ameriphysics, LLCCompany :911 Cross Park Dr.
Knoxville, Tennessee 37923
Address :
Ameriphysics, LLCProject:
398210005Misc Solid19-MAY-16 14:3026-MAY-16
4CVNW AMPH002Project:AMPH002Client ID:
Client
+/-0.0706+/-1.55
+/-0.163+/-0.656+/-0.094+/-0.139+/-0.117+/-0.248+/-0.613+/-0.359+/-0.194+/-0.183+/-0.142+/-0.087+/-0.166
+/-0.0592+/-0.142+/-0.126+/-0.295
Sample ID:
Receive Date:
Client Sample ID:
Matrix:Collect Date:
Collector:
Batch
0.1402.23
0.1651.16
0.1620.2940.152
0.08720.3320.2800.3590.3300.1470.1560.166
0.09960.2120.2180.324
The following Prep Methods were performed:
Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1
Method Description Analyst Date Time Prep Batch
Method
The following Analytical Methods were performed:
1Method Description
1
DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments
UU
UU
UIU
UU
U
UU
UI
Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65
Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"
Uncertainty
0.02931.621.36
0.431-0.0091
0.000.0238
7.9424.02.52
0.01260.0618
1.290.1020.564
-0.03780.0111
0.002.19
RLMDC
Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).
Page 7 of 24
Certificate of Analysis
GEL LABORATORIES LLC2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com
Report Date: June 1, 2016
Rad Gamma Spec Analysis
Parameter Result UnitsQualifier Analyst Date Time
15704721139pCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/gpCi/g
05/31/16MXR1
DF
Mr. Paul JonesContact:
Ameriphysics, LLCCompany :911 Cross Park Dr.
Knoxville, Tennessee 37923
Address :
Ameriphysics, LLCProject:
398210006Misc Solid20-MAY-16 08:3026-MAY-16
5CVHW AMPH002Project:AMPH002Client ID:
Client
+/-0.0781+/-1.45
+/-0.167+/-0.564
+/-0.0906+/-0.280+/-0.164+/-0.224+/-0.479+/-0.354+/-0.160+/-0.180+/-0.149
+/-0.0879+/-0.167
+/-0.0548+/-0.145+/-0.125+/-0.290
Sample ID:
Receive Date:
Client Sample ID:
Matrix:Collect Date:
Collector:
Batch
0.1701.56
0.1701.03
0.1630.0722
0.1670.0816
0.3030.2910.2870.3070.1450.1580.173
0.09840.2250.1990.337
The following Prep Methods were performed:
Dry Soil Prep Dry Soil Prep GL-RAD-A-021 05/26/16 15703781531CXC1
Method Description Analyst Date Time Prep Batch
Method
The following Analytical Methods were performed:
1Method Description
1
DOE HASL 300, 4.5.2.3/Ga-01-RAnalyst Comments
UU
UU
UIU
UU
U
UU
UI
Antimony-124Cadmium-109Cesium-134Chromium-51Cobalt-56Cobalt-57Cobalt-58Cobalt-60Europium-152Europium-154Europium-155Iron-59Manganese-54Niobium-95Scandium-46Silver-108mSilver-110mSodium-22Zinc-65
Gammaspec, Gamma, Solid - Client List "Dry Weight Corrected"
Uncertainty
0.04770.5340.6680.044
0.005490.00
0.09233.9313.71.31
-0.105-0.112
0.2940.00833
0.2580.003320.0237
0.000.851
RLMDC
Notes:Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).
Page 8 of 24
Pages 9 - 14 left out intentionally.
Samples not related to this project.
QC Summary
GEL LABORATORIES LLC2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com
Rad Gamma Spec1570472Batch
Antimony-124
Cadmium-109
Cesium-134
Chromium-51
Cobalt-56
Cobalt-57
Cobalt-58
Cobalt-60
Europium-152
Europium-154
Europium-155
Iron-59
Manganese-54
Niobium-95
Scandium-46
Silver-108m
Silver-110m
Sodium-22
Zinc-65
Americium-241
Parmname
Mr. Paul JonesContact:
Ameriphysics, LLC911 Cross Park Dr.Knoxville, Tennessee
June 1, 2016Report Date:
Units
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
Anlst Date Time
MXR1 06/01/16 06:51
06/01/16 06:35
QC
0.0424
0.238
1.84
-0.58
-0.0179
0.00
0.0165
15.3
42.0
4.45
0.313
0.194
1.70
0.0863
0.777
0.00738
0.0882
0.00
1.17
550
NOM Sample
0.0346
1.07
1.94
-0.637
-0.0918
0.00
0.0309
15.9
43.2
4.41
0.308
0.0514
1.26
0.040
0.792
-0.0743
0.0465
0.00
1.03
Range
N/A
N/A
(0%-20%)
N/A
N/A
N/A
N/A
(0%-20%)
(0%-20%)
(0%-20%)
N/A
N/A
(0%-20%)
N/A
(0% - 100%)
N/A
N/A
N/A
(0% - 100%)
(75%-125%)
Qual
U
U
U
U
UI
U
U
U
U
U
U
UI
QC1203556803 398210001
QC1203556804
N/A
N/A
4.98
N/A
N/A
N/A
N/A
3.53
2.75
0.994
N/A
N/A
30
N/A
1.81
N/A
N/A
N/A
12.8
REC%
112489
DUP
LCS
398210Workorder:
U
U
U
U
UI
U
U
U
U
U
U
UI
+/-0.111
+/-2.98
+/-0.220
+/-1.06
+/-0.135
+/-0.218
+/-0.203
+/-0.395
+/-0.884
+/-0.452
+/-0.311
+/-0.274
+/-0.236
+/-0.127
+/-0.241
+/-0.083
+/-0.202
+/-0.159
+/-0.432
+/-0.140
+/-3.08
+/-0.345
+/-1.49
+/-0.202
+/-0.304
+/-0.235
+/-0.553
+/-1.37
+/-0.673
+/-0.478
+/-0.428
+/-0.341
+/-0.232
+/-0.324
+/-0.121
+/-0.311
+/-0.237
+/-0.781
*
RPD%
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Page 1 of 4
Page 15 of 24
QC Summary
GEL LABORATORIES LLC2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com
Rad Gamma Spec1570472Batch
Cesium-137
Antimony-124
Cadmium-109
Cesium-134
Chromium-51
Cobalt-56
Cobalt-57
Cobalt-58
Cobalt-60
Europium-152
Europium-154
Europium-155
Iron-59
Manganese-54
Niobium-95
Scandium-46
Silver-108m
Silver-110m
Sodium-22
Zinc-65
Antimony-124
Parmname Units
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
Anlst Date Time
MXR1 06/01/16 06:35
06/01/16 06:50
QC
177
0.896
455
-0.646
-1.63
1.08
1.89
-0.0386
160
0.769
-0.569
-1.28
1.40
-0.0956
-0.754
-1.05
-0.0446
0.448
-0.186
3.99
-0.0143
NOM Sample Range
(75%-125%)
(75%-125%)
Qual
U
U
U
U
U
U
U
U
U
U
U
U
U
U
U
UQC1203556802
REC%
97.7
94.9
181
168
MB
398210Workorder:
+/-12.4
+/-3.55
+/-0.721
+/-25.6
+/-0.879
+/-5.30
+/-1.12
+/-0.707
+/-0.838
+/-3.88
+/-2.17
+/-1.27
+/-1.50
+/-1.99
+/-0.854
+/-0.745
+/-0.974
+/-0.699
+/-1.29
+/-0.446
+/-2.10
RPD%
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Page 2 of 4
Page 16 of 24
QC Summary
GEL LABORATORIES LLC2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com
Rad Gamma Spec1570472Batch
Cadmium-109
Cesium-134
Chromium-51
Cobalt-56
Cobalt-57
Cobalt-58
Cobalt-60
Europium-152
Europium-154
Europium-155
Iron-59
Manganese-54
Niobium-95
Scandium-46
Silver-108m
Silver-110m
Sodium-22
Zinc-65
Parmname Units
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
pCi/g
Anlst Date Time
MXR1 06/01/16 06:50
QC
0.0303
0.00601
-0.179
-0.00336
-0.0122
0.0175
-0.01
0.0399
-0.0233
-0.0596
-0.0466
-0.00714
0.00867
-0.00557
0.0506
-0.00265
-0.00731
0.0433
NOM Sample RangeQual
U
U
U
U
U
U
U
U
U
U
U
U
U
U
U
U
U
U
The Qualifiers in this report are defined as follows:
REC%
398210Workorder:
**
<
Analyte is a Tracer compound
Result is less than value reported
+/-0.0672
+/-0.485
+/-0.0226
+/-0.211
+/-0.0244
+/-0.016
+/-0.0345
+/-0.0247
+/-0.0688
+/-0.0834
+/-0.072
+/-0.0526
+/-0.0238
+/-0.0189
+/-0.0269
+/-0.0202
+/-0.0368
+/-0.0295
+/-0.0511
RPD%
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Uncertainty
Notes:
Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).
Page 3 of 4
Page 17 of 24
QC Summary
GEL LABORATORIES LLC2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com
Parmname
Page 4 of 4
Units Anlst Date TimeQCNOM Sample RangeQual REC%
398210Workorder:
>
BD
FA
H
J
K
L
M
M
N/A
N1
ND
NJ
Q
R
U
UI
UJ
UL
X
Y
^
h
Result is greater than value reported
Results are either below the MDC or tracer recovery is low
Failed analysis.
Analytical holding time was exceeded
Value is estimated
Analyte present. Reported value may be biased high. Actual value is expected to be lower.
Analyte present. Reported value may be biased low. Actual value is expected to be higher.
M if above MDC and less than LLD
REMP Result > MDC/CL and < RDL
RPD or %Recovery limits do not apply.
See case narrative
Analyte concentration is not detected above the detection limit
Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier
One or more quality control criteria have not been met. Refer to the applicable narrative or DER.
Sample results are rejected
Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.
Gamma Spectroscopy--Uncertain identification
Gamma Spectroscopy--Uncertain identification
Not considered detected. The associated number is the reported concentration, which may be inaccurate due to a low bias.
Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier
Other specific qualifiers were required to properly define the results. Consult case narrative.
RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL. Qualifier Not Applicable for Radiochemistry.
Preparation or preservation holding time was exceeded
N/A indicates that spike recovery limits do not apply when sample concentration exceeds spike conc. by a factor of 4 or more or %RPD not applicable.^ The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptance criteria when the sample is greater thanfive times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than 5X the RL, a control limit of +/- theRL is used to evaluate the DUP result.* Indicates that a Quality Control parameter was not within specifications.For PS, PSD, and SDILT results, the values listed are the measured amounts, not final concentrations.
Where the analytical method has been performed under NELAP certification, the analysis has met all of therequirements of the NELAC standard unless qualified on the QC Summary.
RPD%
Page 18 of 24
Radiochemistry Technical Case Narrative
Ameriphysics, LLC (AMPH) SDG #: 398210
Product: Gammaspec, Gamma, Solid - Client List Analytical Method: DOE HASL 300, 4.5.2.3/Ga-01-R Analytical Procedure: GL-RAD-A-013 REV# 25 Analytical Batch: 1570472 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 20 Preparation Batch: 1570378
The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 398210001 1CVF 398210002 6CVF 398210003 2CVEW 398210004 3CVWW 398210005 4CVNW 398210006 5CVHW 398210007 1CVF 398210008 6CVF 398210009 2CVWW 398210010 3CVNW 398210011 4CVSW 398210012 5CVEW 1203556802 Method Blank (MB) 1203556803 398210001(1CVF) Sample Duplicate (DUP) 1203556804 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis.
Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods andprocedures for initial calibration, continuing calibration, instrument controls and process controls whereapplicable, with the following exceptions. Quality Control (QC) Information QC Information All of the QC samples meet the required acceptance limits with the following exceptions: The sample and theduplicate, 1203556803 (1CVFDUP) and 398210001 (1CVF), did not meet the Mn-54 relative percent differencerequirement (0-20%); however, they do meet the relative error ratio requirement (0-3) with a value of 1.76. Qualifier Information
Page 19 of 24
Qualifier Reason Analyte Sample Client Sample
UIData rejected due to highcounting uncertainty.
Cesium-134 398210012 5CVEW
UIData rejected due to high peak-width.
Cadmium-109 398210007 1CVF
UIData rejected due to interference.
Cobalt-57 398210003 2CVEW
398210006 5CVHW
398210010 3CVNW
Sodium-22 398210003 2CVEW
398210009 2CVWW
UIData rejected due to low abundance.
Cobalt-57 398210001 1CVF
398210002 6CVF
398210004 3CVWW
398210005 4CVNW
398210007 1CVF
398210008 6CVF
1203556803 1CVF(398210001DUP)
Niobium-95 398210003 2CVEW
Silver-110m 398210008 6CVF
Sodium-22 398210001 1CVF
398210005 4CVNW
398210006 5CVHW
398210007 1CVF
398210012 5CVEW
1203556803 1CVF(398210001DUP)
Zinc-65 398210002 6CVF
398210008 6CVF
Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of therequirements of the NELAC standard unless otherwise noted in the analytical case narrative.
Page 20 of 24
Page 21 of 24
Page 22 left out intentionally.
Chain of Custody not related to this project.
Page 23 of 24
State CertificationAlaska
ArkansasCLIA
California Colorado
ConnecticutDelaware
DoD ELAP/ ISO17025 A2LAFlorida NELAP
Foreign Soils PermitGeorgia
Georgia SDWAHawaii
Idaho ChemistryIdaho Radiochemistry
Illinois NELAPIndiana
Kansas NELAPKentucky SDWA
Kentucky WastewaterLouisiana NELAPLouisiana SDWA
MarylandMassachusetts
MichiganMississippiNebraskaNevada
New Hampshire NELAPNew Jersey NELAP
New MexicoNew York NELAP
North CarolinaNorth Carolina SDWA
North DakotaOklahoma
Pennsylvania NELAPS.Carolina Radchem
South Carolina ChemistryTennessee
Texas NELAPUtah NELAP
VermontVirginia NELAP
WashingtonWest Virginia
UST−011088−0651
42D09040462940
SC00012PH−0169SC000122567.01E87156
P330−15−00283, P330−15−00253SC00012
967SC00012SC00012SC00012200029
C−SC−01E−10332
9012990129
03046 (AI33904)LA160006
270M−SC012
9976SC00012
NE−OS−26−13SC000122016−1
205415SC002
SC0001211501233
45709R−1589904
68−004851012000210120001TN 02934
T104704235−16−11SC000122016−20
VT87156460202C780
997404
List of current GEL Certifications as of 01 June 2016
Page 24 of 24
Attachment 2 RESRAD-BUILD DCGLactivation Modeling for Radionuclides of Concern
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 1 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld ================================================ ================================================ === === === RESRAD-BUILD Table of Contents === === === ================================================ ================================================
RESRAD-BUILD Input Parameters............ 2 Building Information..................... 3 Source Information....................... 4 For time = 0.00E+00 yr Time Specific Parameters.............. 5 Receptor-Source Dose Summary.......... 6 Dose by Pathway Detail................ 7 Dose by Nuclide Detail................ 8 For time = 1.00E+00 yr Time Specific Parameters.............. 9 Receptor-Source Dose Summary.......... 10 Dose by Pathway Detail................ 11 Dose by Nuclide Detail................ 12 Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 2 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld ================================================ ================================================ === === === RESRAD-BUILD Input Parameters === === === ================================================ ================================================ Number of Sources : 1 Number of Receptors: 1 Total Time : 3.650000E+02 days Fraction Inside : 5.000000E-01 ========== Receptor Information ========== Receptor Room x y z FracTime Inhalation Ingestion(Dust) [m] [m] [m] [m3/day] [m2/hr] 1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04 === Receptor-Source Shielding Relationship === Receptor Source Density Thickness Material [g/cm3] [cm] ——————————————————————————————————————————————— 1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 3 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld ======== Building Information ======== Building Air Exchange Rate: 8.00E-01 1/hr Height[m] Air Exchanges [m3/hr] Area [m2] ******************************* * * * * * <=Q01: 7.20E+01 H1: 2.500 * Room 1 * Q10 : 7.20E+01 * LAMBDA: 8.00E-01 * Area 36.000 * * * * ******************************* Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 4 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Pathway :: Direct Ingestion Rate: 0.000E+00 [gm/hr] Fraction released to air: 1.000E-01
Containment :: Number of Regions: 1 Contaminated Region: 1 Region : 1 Thickness [cm] :1.50E+01 Density [g/cm3] :2.40E+00 Material :Concrete Erosion Rate [cm/day] :2.40E-08
Contamination:: Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity) ——————— ————————————— ——————————————————————————————————— Ingestion Inhalation Submersion [pCi/g] [mrem/pCi] [mrem/pCi] [mrem/yr/ (pCi/m3)] FE-55 1.000E+00 6.070E-07 2.690E-06 0.000E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 5 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years ================================================ ================================================ === Assessment for Time: 1 === === Time =0.00E+00 yr === ================================================ ================================================ ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Pathway :: Direct Ingestion Rate : 0.000E+00 [gm/hr] Fraction released to air: 1.000E-01
Containment :: Number of Regions: 1 Contaminated Region: 1 Region : 1 Thickness [cm] :1.50E+01 Fraction Contaminated :1.00E+00 Density [g/cm3] :2.40E+00
Contamination:: Nuclide Concentration [pCi/g] FE-55 1.000E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 6 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years ================================================ ================================================ === === === RESRAD-BUILD Dose Tables === === === ================================================ ================================================ Source Contributions to Receptor Doses ====================================== [mrem] Source Total 1 Receptor 1 1.16E-08 1.16E-08 Total 1.16E-08 1.16E-08
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 7 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years Pathway Detail of Doses ======================= [mrem] Source: 1 Receptor External Deposition Immersion Inhalation Radon Ingestion 1 0.00E+00 0.00E+00 0.00E+00 7.26E-09 0.00E+00 4.30E-09 Total 0.00E+00 0.00E+00 0.00E+00 7.26E-09 0.00E+00 4.30E-09
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 8 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years Nuclide Detail of Doses ======================= [mrem] Source: 1 Nuclide Receptor Total 1 FE-55 1.16E-08 1.16E-08
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 9 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years ================================================ ================================================ === Assessment for Time: 2 === === Time =1.00E+00 yr === ================================================ ================================================ ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Pathway :: Direct Ingestion Rate : 0.000E+00 [gm/hr] Fraction released to air: 1.000E-01
Containment :: Number of Regions: 1 Contaminated Region: 1 Region : 1 Thickness [cm] :1.50E+01 Fraction Contaminated :1.00E+00 Density [g/cm3] :2.40E+00
Contamination:: Nuclide Concentration [pCi/g] FE-55 7.736E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 10 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years ================================================ ================================================ === === === RESRAD-BUILD Dose Tables === === === ================================================ ================================================ Source Contributions to Receptor Doses ====================================== [mrem] Source Total 1 Receptor 1 8.94E-09 8.94E-09 Total 8.94E-09 8.94E-09
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 11 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years Pathway Detail of Doses ======================= [mrem] Source: 1 Receptor External Deposition Immersion Inhalation Radon Ingestion 1 0.00E+00 0.00E+00 0.00E+00 5.62E-09 0.00E+00 3.33E-09 Total 0.00E+00 0.00E+00 0.00E+00 5.62E-09 0.00E+00 3.33E-09
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 12 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years Nuclide Detail of Doses ======================= [mrem] Source: 1 Nuclide Receptor Total 1 FE-55 8.94E-09 8.94E-09
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:36:45 Page: 13 ** Title : Fe-55 @ 1 pCi/g Input File : site1.bld Full Summary ================================================ ================================================ === === === RESRAD-BUILD Dose (Time) Tables === === === ================================================ ================================================ Receptor Dose Received for the Exposure Duration ================================================ (mrem) Evaluation Time [yr] 0.00E+00 1.00E+00 ———————— ———————— 1 1.16E-08 8.94E-09 Receptor Dose/Yr Averaged Over Exposure Duration ================================================ (mrem/yr) Evaluation Time [yr] 0.00E+00 1.00E+00 ———————— ———————— 1 1.16E-08 8.95E-09
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 1 ** Title : H-3 @ 1 pCi/g Input File : site1.bld ================================================ ================================================ === === === RESRAD-BUILD Table of Contents === === === ================================================ ================================================
RESRAD-BUILD Input Parameters............ 2 Building Information..................... 3 Source Information....................... 4 For time = 0.00E+00 yr Time Specific Parameters.............. 5 Receptor-Source Dose Summary.......... 6 Dose by Pathway Detail................ 7 Dose by Nuclide Detail................ 8 For time = 1.00E+00 yr Time Specific Parameters.............. 9 Receptor-Source Dose Summary.......... 10 Dose by Pathway Detail................ 11 Dose by Nuclide Detail................ 12 Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 2 ** Title : H-3 @ 1 pCi/g Input File : site1.bld ================================================ ================================================ === === === RESRAD-BUILD Input Parameters === === === ================================================ ================================================ Number of Sources : 1 Number of Receptors: 1 Total Time : 3.650000E+02 days Fraction Inside : 5.000000E-01 ========== Receptor Information ========== Receptor Room x y z FracTime Inhalation Ingestion(Dust) [m] [m] [m] [m3/day] [m2/hr] 1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04 === Receptor-Source Shielding Relationship === Receptor Source Density Thickness Material [g/cm3] [cm] ——————————————————————————————————————————————— 1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 3 ** Title : H-3 @ 1 pCi/g Input File : site1.bld ======== Building Information ======== Building Air Exchange Rate: 8.00E-01 1/hr Height[m] Air Exchanges [m3/hr] Area [m2] ******************************* * * * * * <=Q01: 7.20E+01 H1: 2.500 * Room 1 * Q10 : 7.20E+01 * LAMBDA: 8.00E-01 * Area 36.000 * * * * ******************************* Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 4 ** Title : H-3 @ 1 pCi/g Input File : site1.bld ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Tritium Volume Parameters :: Total Thickness: 1.000E+01 [cm] Dry Thickness: 0.000E+00 [cm] Volumetric Water Content: 3.000E-02 Wall Total Porosity: 1.000E-01 Volatization Fraction: 1.000E+00 Wall Density: 2.400E+00 [gm/cm3] Humidity: 8.000E+00 [gm/m3] Erosion rate: 2.400E-08 [cm/d] Direct Ingestion Rate: 0.000E+00 [gm/hr] Fraction released to air: 1.000E-01
Contamination:: Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity) ——————— ————————————— ——————————————————————————————————— Ingestion Inhalation Submersion [pCi/g] [mrem/pCi] [mrem/pCi] [mrem/yr/ (pCi/m3)] H-3 1.000E+00 6.400E-08 6.400E-08 3.866E-08
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 5 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years ================================================ ================================================ === Assessment for Time: 1 === === Time =0.00E+00 yr === ================================================ ================================================ ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Contamination :: Total Thickness: 1.000E+01 [cm] Dry Thickness: 0.000E+00 [cm] Volumetric Water Content: 3.000E-02 Wall Total Porosity: 1.000E-01 Volatization Fraction: 1.000E+00 Wall Density: 2.400E+00 [gm/cm3] Humidity: 8.000E+00 [gm/m3] Erosion Rate: 2.400E-08 [cm/d]
Contamination:: Tritium in Volume Source Initial Volatile Activity [pCi] : 8640000.00 Remaining Volatization Time [yr] : 0.417022973 Unvolatizable activity remaining [pCi]: 0.00000000E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 6 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years ================================================ ================================================ === === === RESRAD-BUILD Dose Tables === === === ================================================ ================================================ Source Contributions to Receptor Doses ====================================== [mrem] Source Total 1 Receptor 1 9.67E-03 9.67E-03 Total 9.67E-03 9.67E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 7 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years Pathway Detail of Doses ======================= [mrem] Source: 1 Receptor External Deposition Immersion Inhalation Radon Ingestion 1 0.00E+00 0.00E+00 2.14E-07 3.49E-03 0.00E+00 6.18E-03 Total 0.00E+00 0.00E+00 2.14E-07 3.49E-03 0.00E+00 6.18E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 8 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 0.00000000E+00 years Nuclide Detail of Doses ======================= [mrem] Source: 1 Nuclide Receptor Total 1 H-3 9.67E-03 9.67E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 9 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years ================================================ ================================================ === Assessment for Time: 2 === === Time =1.00E+00 yr === ================================================ ================================================ ======== Source Information ======== Source: 1 Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m] Geometry:: Type: Volume Area:3.60E+01 [m2] Direction: x Contamination :: Total Thickness: 1.000E+01 [cm] Dry Thickness: 0.000E+00 [cm] Volumetric Water Content: 3.000E-02 Wall Total Porosity: 1.000E-01 Volatization Fraction: 1.000E+00 Wall Density: 2.400E+00 [gm/cm3] Humidity: 8.000E+00 [gm/m3] Erosion Rate: 2.400E-08 [cm/d]
Contamination:: Tritium in Volume Source Initial Volatile Activity [pCi] : 8640000.00 Remaining Volatization Time [yr] : 0.00000000E+00 Unvolatizable activity remaining [pCi]: 0.00000000E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 10 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years ================================================ ================================================ === === === RESRAD-BUILD Dose Tables === === === ================================================ ================================================ Source Contributions to Receptor Doses ====================================== [mrem] Source Total 1 Receptor 1 0.00E+00 0.00E+00 Total 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 11 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years Pathway Detail of Doses ======================= [mrem] Source: 1 Receptor External Deposition Immersion Inhalation Radon Ingestion 1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 12 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Evaluation Time: 1.00000000 years Nuclide Detail of Doses ======================= [mrem] Source: 1 Nuclide Receptor Total 1 H-3 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/30/16 09:41:30 Page: 13 ** Title : H-3 @ 1 pCi/g Input File : site1.bld Full Summary ================================================ ================================================ === === === RESRAD-BUILD Dose (Time) Tables === === === ================================================ ================================================ Receptor Dose Received for the Exposure Duration ================================================ (mrem) Evaluation Time [yr] 0.00E+00 1.00E+00 ———————— ———————— 1 9.67E-03 0.00E+00 Receptor Dose/Yr Averaged Over Exposure Duration ================================================ (mrem/yr) Evaluation Time [yr] 0.00E+00 1.00E+00 ———————— ———————— 1 9.67E-03 0.00E+00
Attachment 3 RESRAD-BUILD DCGLsurface Modeling for Radionuclides of Concern
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 1 **
Title : Ag-108m
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 2 **
Title : Ag-108m
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 3 **
Title : Ag-108m
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 4 **
Title : Ag-108m
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
AG-108M 2.800E+06 3.432E-06 1.275E-04 4.108E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 5 **
Title : Ag-108m
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
AG-108M 2.800E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 6 **
Title : Ag-108m
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.50E+01 2.50E+01
Total 2.50E+01 2.50E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 7 **
Title : Ag-108m
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.99E+01 1.57E+00 1.59E-02 3.25E+00 0.00E+00 2.33E-01
Total 1.99E+01 1.57E+00 1.59E-02 3.25E+00 0.00E+00 2.33E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 8 **
Title : Ag-108m
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
AG-108M 2.50E+01 2.50E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 9 **
Title : Ag-108m
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
AG-108M 1.392E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 10 **
Title : Ag-108m
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 1.32E+01 1.32E+01
Total 1.32E+01 1.32E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 11 **
Title : Ag-108m
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.32E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 1.32E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 12 **
Title : Ag-108m
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
AG-108M 1.32E+01 1.32E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:51:11 Page: 13 **
Title : Ag-108m
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.50E+01 1.32E+01
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.50E+01 1.32E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 1 **
Title : Ag-110m
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 2 **
Title : Ag-110m
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 3 **
Title : Ag-110m
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 4 **
Title : Ag-110m
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
AG-110M 3.000E+06 4.865E-06 3.617E-05 7.157E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 5 **
Title : Ag-110m
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
AG-110M 3.000E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 6 **
Title : Ag-110m
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.48E+01 2.48E+01
Total 2.48E+01 2.48E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 7 **
Title : Ag-110m
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.36E+01 8.04E-01 9.13E-03 3.03E-01 0.00E+00 1.02E-01
Total 2.36E+01 8.04E-01 9.13E-03 3.03E-01 0.00E+00 1.02E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 8 **
Title : Ag-110m
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
AG-110M 2.48E+01 2.48E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 9 **
Title : Ag-110m
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
AG-110M 5.445E+05
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 10 **
Title : Ag-110m
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 5.41E+00 5.41E+00
Total 5.41E+00 5.41E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 11 **
Title : Ag-110m
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 5.41E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 5.41E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 12 **
Title : Ag-110m
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
AG-110M 5.41E+00 5.41E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:49:54 Page: 13 **
Title : Ag-110m
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.48E+01 5.41E+00
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.48E+01 5.41E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 1 **
Title : Cd-109
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 2 **
Title : Cd-109
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 3 **
Title : Cd-109
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 4 **
Title : Cd-109
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
CD-109 5.200E+07 5.901E-06 5.135E-05 1.547E-05
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 5 **
Title : Cd-109
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CD-109 5.200E+07
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 6 **
Title : Cd-109
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.46E+01 2.46E+01
Total 2.46E+01 2.46E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 7 **
Title : Cd-109
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 8.87E+00 4.14E-01 5.44E-04 1.19E+01 0.00E+00 3.51E+00
Total 8.87E+00 4.14E-01 5.44E-04 1.19E+01 0.00E+00 3.51E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 8 **
Title : Cd-109
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CD-109 2.46E+01 2.46E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 9 **
Title : Cd-109
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CD-109 1.506E+07
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 10 **
Title : Cd-109
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 3.32E+00 3.32E+00
Total 3.32E+00 3.32E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 11 **
Title : Cd-109
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 3.32E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 3.32E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 12 **
Title : Cd-109
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CD-109 3.32E+00 3.32E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:52:25 Page: 13 **
Title : Cd-109
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.46E+01 3.32E+00
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.47E+01 3.33E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 1 **
Title : Co-56
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 2 **
Title : Co-56
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 3 **
Title : Co-56
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 4 **
Title : Co-56
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
CO-56 7.400E+06 5.676E-06 1.784E-05 9.628E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 5 **
Title : Co-56
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CO-56 7.400E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 6 **
Title : Co-56
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.48E+01 2.48E+01
Total 2.48E+01 2.48E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 7 **
Title : Co-56
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.43E+01 3.49E-01 7.51E-03 9.13E-02 0.00E+00 6.44E-02
Total 2.43E+01 3.49E-01 7.51E-03 9.13E-02 0.00E+00 6.44E-02
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 8 **
Title : Co-56
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CO-56 2.48E+01 2.48E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 9 **
Title : Co-56
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CO-56 1.495E+05
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 10 **
Title : Co-56
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 5.66E-01 5.66E-01
Total 5.66E-01 5.66E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 11 **
Title : Co-56
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 5.66E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 5.66E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 12 **
Title : Co-56
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CO-56 5.66E-01 5.66E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:33:23 Page: 13 **
Title : Co-56
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.48E+01 5.66E-01
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.48E+01 5.67E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 1 **
Title : Co-57
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 2 **
Title : Co-57
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 3 **
Title : Co-57
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 4 **
Title : Co-57
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
CO-57 6.600E+07 5.315E-07 4.086E-06 2.952E-04
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 5 **
Title : Co-57
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CO-57 6.600E+07
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 6 **
Title : Co-57
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.49E+01 2.49E+01
Total 2.49E+01 2.49E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 7 **
Title : Co-57
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.30E+01 8.21E-01 8.90E-03 8.09E-01 0.00E+00 2.65E-01
Total 2.30E+01 8.21E-01 8.90E-03 8.09E-01 0.00E+00 2.65E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 8 **
Title : Co-57
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CO-57 2.49E+01 2.49E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 9 **
Title : Co-57
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CO-57 1.297E+07
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 10 **
Title : Co-57
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 5.73E+00 5.73E+00
Total 5.73E+00 5.73E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 11 **
Title : Co-57
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 5.73E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 5.73E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 12 **
Title : Co-57
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CO-57 5.73E+00 5.73E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 09:28:57 Page: 13 **
Title : Co-57
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.49E+01 5.73E+00
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.49E+01 5.74E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 1 **
Title : Co-58
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 2 **
Title : Co-58
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 3 **
Title : Co-58
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 4 **
Title : Co-58
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
CO-58 2.000E+08 1.613E-06 4.910E-06 2.504E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 5 **
Title : Co-58
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CO-58 2.000E+08
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 6 **
Title : Co-58
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.46E+01 2.46E+01
Total 2.46E+01 2.46E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 7 **
Title : Co-58
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.33E+01 3.04E-01 4.49E-02 5.78E-01 0.00E+00 4.13E-01
Total 2.33E+01 3.04E-01 4.49E-02 5.78E-01 0.00E+00 4.13E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 8 **
Title : Co-58
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CO-58 2.46E+01 2.46E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 9 **
Title : Co-58
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CO-58 2.807E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 10 **
Title : Co-58
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 3.74E-01 3.74E-01
Total 3.74E-01 3.74E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 11 **
Title : Co-58
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 3.74E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 3.74E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 12 **
Title : Co-58
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CO-58 3.74E-01 3.74E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:26:57 Page: 13 **
Title : Co-58
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.46E+01 3.74E-01
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.46E+01 3.74E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 1 **
Title : Co-60
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 2 **
Title : Co-60
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 3 **
Title : Co-60
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 4 **
Title : Co-60
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
CO-60 2.100E+06 1.212E-05 9.865E-05 6.629E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 5 **
Title : Co-60
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CO-60 2.100E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 6 **
Title : Co-60
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.40E+01 2.40E+01
Total 2.40E+01 2.40E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 7 **
Title : Co-60
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.05E+01 1.39E+00 1.59E-02 1.55E+00 0.00E+00 5.05E-01
Total 2.05E+01 1.39E+00 1.59E-02 1.55E+00 0.00E+00 5.05E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 8 **
Title : Co-60
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CO-60 2.40E+01 2.40E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 9 **
Title : Co-60
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CO-60 9.206E+05
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 10 **
Title : Co-60
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 1.19E+01 1.19E+01
Total 1.19E+01 1.19E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 11 **
Title : Co-60
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.19E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 1.19E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 12 **
Title : Co-60
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CO-60 1.19E+01 1.19E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:10:46 Page: 13 **
Title : Co-60
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.40E+01 1.19E+01
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.40E+01 1.19E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 1 **
Title : Cr-51
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 2 **
Title : Cr-51
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 3 **
Title : Cr-51
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 4 **
Title : Cr-51
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
CR-51 1.300E+09 6.622E-08 1.505E-07 7.945E-05
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 5 **
Title : Cr-51
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CR-51 1.300E+09
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 6 **
Title : Cr-51
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.50E+01 2.50E+01
Total 2.50E+01 2.50E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 7 **
Title : Cr-51
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.48E+01 1.32E-01 2.13E-03 2.64E-02 0.00E+00 1.96E-02
Total 2.48E+01 1.32E-01 2.13E-03 2.64E-02 0.00E+00 1.96E-02
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 8 **
Title : Cr-51
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CR-51 2.50E+01 2.50E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 9 **
Title : Cr-51
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CR-51 6.984E+04
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 10 **
Title : Cr-51
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 1.41E-03 1.41E-03
Total 1.41E-03 1.41E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 11 **
Title : Cr-51
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.41E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 1.41E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 12 **
Title : Cr-51
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CR-51 1.41E-03 1.41E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:56:16 Page: 13 **
Title : Cr-51
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.50E+01 1.41E-03
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.50E+01 1.41E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 1 **
Title : Cs-134
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 2 **
Title : Cs-134
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 3 **
Title : Cs-134
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 4 **
Title : Cs-134
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
CS-134 3.600E+06 3.302E-05 2.081E-05 3.983E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 5 **
Title : Cs-134
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CS-134 3.600E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 6 **
Title : Cs-134
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.44E+01 2.44E+01
Total 2.44E+01 2.44E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 7 **
Title : Cs-134
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.10E+01 1.17E+00 1.24E-02 4.26E-01 0.00E+00 1.76E+00
Total 2.10E+01 1.17E+00 1.24E-02 4.26E-01 0.00E+00 1.76E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 8 **
Title : Cs-134
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CS-134 2.44E+01 2.44E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 9 **
Title : Cs-134
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
CS-134 1.286E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 10 **
Title : Cs-134
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 9.84E+00 9.84E+00
Total 9.84E+00 9.84E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 11 **
Title : Cs-134
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 9.84E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 9.84E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 12 **
Title : Cs-134
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
CS-134 9.84E+00 9.84E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:09:44 Page: 13 **
Title : Cs-134
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.44E+01 9.84E+00
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.44E+01 9.84E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 1 **
Title : Eu-152
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 2 **
Title : Eu-152
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 3 **
Title : Eu-152
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 4 **
Title : Eu-152
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
GD-152 0.000E+00 7.252E-05 1.095E-01 0.000E+00
EU-152 4.000E+06 2.919E-06 9.955E-05 2.973E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 5 **
Title : Eu-152
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
GD-152 0.000E+00
EU-152 4.000E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 6 **
Title : Eu-152
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.45E+01 2.45E+01
Total 2.45E+01 2.45E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 7 **
Title : Eu-152
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.94E+01 1.44E+00 1.53E-02 3.36E+00 0.00E+00 2.62E-01
Total 1.94E+01 1.44E+00 1.53E-02 3.36E+00 0.00E+00 2.62E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 8 **
Title : Eu-152
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
GD-152 1.24E-11 1.24E-11
EU-152 2.45E+01 2.45E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 9 **
Title : Eu-152
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
GD-152 1.251E-08
EU-152 1.898E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 10 **
Title : Eu-152
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 1.22E+01 1.22E+01
Total 1.22E+01 1.22E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 11 **
Title : Eu-152
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.22E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 1.22E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 12 **
Title : Eu-152
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
GD-152 0.00E+00 0.00E+00
EU-152 1.22E+01 1.22E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:11:46 Page: 13 **
Title : Eu-152
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.45E+01 1.22E+01
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.45E+01 1.22E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 1 **
Title : Eu-154
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 2 **
Title : Eu-154
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 3 **
Title : Eu-154
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 4 **
Title : Eu-154
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
EU-154 3.700E+06 4.302E-06 1.288E-04 3.230E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 5 **
Title : Eu-154
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
EU-154 3.700E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 6 **
Title : Eu-154
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.46E+01 2.46E+01
Total 2.46E+01 2.46E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 7 **
Title : Eu-154
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.90E+01 1.37E+00 1.48E-02 3.87E+00 0.00E+00 3.43E-01
Total 1.90E+01 1.37E+00 1.48E-02 3.87E+00 0.00E+00 3.43E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 8 **
Title : Eu-154
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
EU-154 2.46E+01 2.46E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 9 **
Title : Eu-154
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
EU-154 1.710E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 10 **
Title : Eu-154
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 1.17E+01 1.17E+01
Total 1.17E+01 1.17E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 11 **
Title : Eu-154
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.17E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 1.17E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 12 **
Title : Eu-154
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
EU-154 1.17E+01 1.17E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:12:43 Page: 13 **
Title : Eu-154
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.46E+01 1.17E+01
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.46E+01 1.17E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 1 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 2 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 3 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 4 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
EU-155 5.700E+07 6.892E-07 1.865E-05 1.310E-04
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 5 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
EU-155 5.700E+07
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 6 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.46E+01 2.46E+01
Total 2.46E+01 2.46E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 7 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.50E+01 1.01E+00 8.43E-03 7.88E+00 0.00E+00 7.69E-01
Total 1.50E+01 1.01E+00 8.43E-03 7.88E+00 0.00E+00 7.69E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 8 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
EU-155 2.46E+01 2.46E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 9 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
EU-155 2.478E+07
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 10 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 8.62E+00 8.62E+00
Total 8.62E+00 8.62E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 11 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 8.62E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 8.62E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 12 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
EU-155 8.62E+00 8.62E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:57:45 Page: 13 **
Title : Eu-155 @ 1 pCi/g
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.46E+01 8.62E+00
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.47E+01 8.62E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 1 **
Title : Fe-59
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 2 **
Title : Fe-59
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 3 **
Title : Fe-59
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 4 **
Title : Fe-59
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
FE-59 3.000E+08 3.018E-06 6.667E-06 3.141E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 5 **
Title : Fe-59
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
FE-59 3.000E+08
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 6 **
Title : Fe-59
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.49E+01 2.49E+01
Total 2.49E+01 2.49E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 7 **
Title : Fe-59
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.36E+01 2.00E-01 4.10E-02 5.71E-01 0.00E+00 5.06E-01
Total 2.36E+01 2.00E-01 4.10E-02 5.71E-01 0.00E+00 5.06E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 8 **
Title : Fe-59
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
FE-59 2.49E+01 2.49E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 9 **
Title : Fe-59
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
FE-59 5.112E+05
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 10 **
Title : Fe-59
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 4.40E-02 4.40E-02
Total 4.40E-02 4.40E-02
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 11 **
Title : Fe-59
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 4.40E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 4.40E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 12 **
Title : Fe-59
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
FE-59 4.40E-02 4.40E-02
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 11:09:02 Page: 13 **
Title : Fe-59
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.49E+01 4.40E-02
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.49E+01 4.40E-02
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 1 **
Title : Mn-54
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 2 **
Title : Mn-54
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 3 **
Title : Mn-54
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 4 **
Title : Mn-54
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
MN-54 9.100E+06 1.248E-06 3.018E-06 2.152E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 5 **
Title : Mn-54
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
MN-54 9.100E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 6 **
Title : Mn-54
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.48E+01 2.48E+01
Total 2.48E+01 2.48E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 7 **
Title : Mn-54
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.36E+01 9.14E-01 1.01E-02 9.27E-02 0.00E+00 9.72E-02
Total 2.36E+01 9.14E-01 1.01E-02 9.27E-02 0.00E+00 9.72E-02
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 8 **
Title : Mn-54
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
MN-54 2.48E+01 2.48E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 9 **
Title : Mn-54
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
MN-54 2.025E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 10 **
Title : Mn-54
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 6.72E+00 6.72E+00
Total 6.72E+00 6.72E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 11 **
Title : Mn-54
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 6.72E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 6.72E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 12 **
Title : Mn-54
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
MN-54 6.72E+00 6.72E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:13:55 Page: 13 **
Title : Mn-54
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.48E+01 6.72E+00
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.48E+01 6.72E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 1 **
Title : Na-22
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 2 **
Title : Na-22
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 3 **
Title : Na-22
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 4 **
Title : Na-22
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
NA-22 2.700E+06 5.180E-06 3.450E-06 5.682E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 5 **
Title : Na-22
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
NA-22 2.700E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 6 **
Title : Na-22
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.42E+01 2.42E+01
Total 2.42E+01 2.42E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 7 **
Title : Na-22
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.26E+01 1.34E+00 1.45E-02 5.79E-02 0.00E+00 2.28E-01
Total 2.26E+01 1.34E+00 1.45E-02 5.79E-02 0.00E+00 2.28E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 8 **
Title : Na-22
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
NA-22 2.42E+01 2.42E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 9 **
Title : Na-22
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
NA-22 1.034E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 10 **
Title : Na-22
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 1.14E+01 1.14E+01
Total 1.14E+01 1.14E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 11 **
Title : Na-22
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.14E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 1.14E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 12 **
Title : Na-22
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
NA-22 1.14E+01 1.14E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 10:51:59 Page: 13 **
Title : Na-22
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.42E+01 1.14E+01
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.43E+01 1.14E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 1 **
Title : Nb-95
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 2 **
Title : Nb-95
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 3 **
Title : Nb-95
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 4 **
Title : Nb-95
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
NB-95 6.800E+07 1.158E-06 2.617E-06 1.968E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 5 **
Title : Nb-95
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
NB-95 6.800E+07
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 6 **
Title : Nb-95
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.47E+01 2.47E+01
Total 2.47E+01 2.47E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 7 **
Title : Nb-95
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.45E+01 1.65E-01 3.99E-03 3.49E-02 0.00E+00 2.82E-02
Total 2.45E+01 1.65E-01 3.99E-03 3.49E-02 0.00E+00 2.82E-02
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 8 **
Title : Nb-95
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
NB-95 2.47E+01 2.47E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 9 **
Title : Nb-95
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
NB-95 2.525E+04
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 10 **
Title : Nb-95
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 9.76E-03 9.76E-03
Total 9.76E-03 9.76E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 11 **
Title : Nb-95
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 9.76E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 9.76E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 12 **
Title : Nb-95
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
NB-95 9.76E-03 9.76E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 08/05/16 13:55:06 Page: 13 **
Title : Nb-95
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.47E+01 9.76E-03
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.47E+01 9.76E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 1 **
Title : Sb-124
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 2 **
Title : Sb-124
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 3 **
Title : Sb-124
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 4 **
Title : Sb-124
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
SB-124 1.700E+08 4.550E-06 1.135E-05 4.814E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 5 **
Title : Sb-124
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
SB-124 1.700E+08
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 6 **
Title : Sb-124
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.47E+01 2.47E+01
Total 2.47E+01 2.47E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 7 **
Title : Sb-124
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.27E+01 2.57E-01 5.72E-02 8.86E-01 0.00E+00 7.48E-01
Total 2.27E+01 2.57E-01 5.72E-02 8.86E-01 0.00E+00 7.48E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 8 **
Title : Sb-124
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
SB-124 2.47E+01 2.47E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 9 **
Title : Sb-124
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
SB-124 1.273E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 10 **
Title : Sb-124
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 1.92E-01 1.92E-01
Total 1.92E-01 1.92E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 11 **
Title : Sb-124
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 1.92E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 1.92E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 12 **
Title : Sb-124
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
SB-124 1.92E-01 1.92E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/27/16 12:55:12 Page: 13 **
Title : Sb-124
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.47E+01 1.92E-01
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.47E+01 1.92E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 1 **
Title : Sc-46
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 2 **
Title : Sc-46
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 3 **
Title : Sc-46
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 4 **
Title : Sc-46
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
SC-46 1.600E+09 2.883E-06 1.333E-05 5.251E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 5 **
Title : Sc-46
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
SC-46 1.600E+09
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 6 **
Title : Sc-46
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.50E+01 2.50E+01
Total 2.50E+01 2.50E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 7 **
Title : Sc-46
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 0.00E+00 0.00E+00 9.72E-01 1.62E+01 0.00E+00 7.84E+00
Total 0.00E+00 0.00E+00 9.72E-01 1.62E+01 0.00E+00 7.84E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 8 **
Title : Sc-46
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
SC-46 2.50E+01 2.50E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 9 **
Title : Sc-46
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
SC-46 3.929E+07
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 10 **
Title : Sc-46
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 0.00E+00 0.00E+00
Total 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 11 **
Title : Sc-46
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 12 **
Title : Sc-46
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
SC-46 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:14:54 Page: 13 **
Title : Sc-46
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.50E+01 0.00E+00
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.50E+01 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 1 **
Title : Zn-65
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Table of Contents ===
=== ===
================================================
================================================
RESRAD-BUILD Input Parameters............ 2
Building Information..................... 3
Source Information....................... 4
For time = 0.00E+00 yr
Time Specific Parameters.............. 5
Receptor-Source Dose Summary.......... 6
Dose by Pathway Detail................ 7
Dose by Nuclide Detail................ 8
For time = 1.00E+00 yr
Time Specific Parameters.............. 9
Receptor-Source Dose Summary.......... 10
Dose by Pathway Detail................ 11
Dose by Nuclide Detail................ 12
Full Summary............................. 13
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 2 **
Title : Zn-65
Input File : site1.bld
================================================
================================================
=== ===
=== RESRAD-BUILD Input Parameters ===
=== ===
================================================
================================================
Number of Sources : 1
Number of Receptors: 1
Total Time : 3.650000E+02 days
Fraction Inside : 5.000000E-01
========== Receptor Information ==========
Receptor Room x y z FracTime Inhalation Ingestion(Dust)
[m] [m] [m] [m3/day] [m2/hr]
1 1 1.000 1.000 1.000 1.000 1.80E+01 1.00E-04
=== Receptor-Source Shielding Relationship ===
Receptor Source Density Thickness Material
[g/cm3] [cm]
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
1 1 2.40E+00 0.00E+00 Concrete
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 3 **
Title : Zn-65
Input File : site1.bld
======== Building Information ========
Building Air Exchange Rate: 8.00E-01 1/hr
Height[m] Air Exchanges [m3/hr]
Area [m2]
*******************************
* *
* *
* <=Q01: 7.20E+01
H1: 2.500 * Room 1 * Q10 : 7.20E+01
* LAMBDA: 8.00E-01 *
Area 36.000 * *
* *
*******************************
Deposition velocity: 1.00E-02 [m/s] Resuspension Rate: 5.00E-07 [1/s]
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 4 **
Title : Zn-65
Input File : site1.bld
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00[m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination::
Nuclide Concentration Dose Conversion Factor (Library: FGR 13 Morbidity)
— — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — — —
Ingestion Inhalation Submersion
[dpm/m2] [mrem/dpm] [mrem/dpm] [mrem/yr/
(dpm/m3)]
ZN-65 1.400E+07 6.486E-06 9.189E-06 1.526E-03
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 5 **
Title : Zn-65
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== Assessment for Time: 1 ===
=== Time =0.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 5.000E-01
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
ZN-65 1.400E+07
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 6 **
Title : Zn-65
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 2.44E+01 2.44E+01
Total 2.44E+01 2.44E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 7 **
Title : Zn-65
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 2.27E+01 7.61E-01 8.89E-03 3.51E-01 0.00E+00 6.21E-01
Total 2.27E+01 7.61E-01 8.89E-03 3.51E-01 0.00E+00 6.21E-01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 8 **
Title : Zn-65
Input File : site1.bld
Evaluation Time: 0.00000000E+00 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
ZN-65 2.44E+01 2.44E+01
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 9 **
Title : Zn-65
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== Assessment for Time: 2 ===
=== Time =1.00E+00 yr ===
================================================
================================================
======== Source Information ========
Source: 1
Location:: Room : 1 x: 0.00 y: 0.00 z: 0.00 [m]
Geometry:: Type: Area Area:3.60E+01 [m2] Direction: x
Pathway ::
Direct Ingestion Rate: 0.000E+00 [1/hr]
Fraction released to air: 1.000E-01
Removable fraction: 0.000E+00
Time to Remove: 3.650E+02 [day]
Contamination:: Nuclide Concentration
[dpm/m2]
ZN-65 2.480E+06
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 10 **
Title : Zn-65
Input File : site1.bld
Evaluation Time: 1.00000000 years
================================================
================================================
=== ===
=== RESRAD-BUILD Dose Tables ===
=== ===
================================================
================================================
Source Contributions to Receptor Doses
======================================
[mrem]
Source Total
1
Receptor 1 5.06E+00 5.06E+00
Total 5.06E+00 5.06E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 11 **
Title : Zn-65
Input File : site1.bld
Evaluation Time: 1.00000000 years
Pathway Detail of Doses
=======================
[mrem]
Source: 1
Receptor External Deposition Immersion Inhalation Radon Ingestion
1 5.06E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Total 5.06E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 12 **
Title : Zn-65
Input File : site1.bld
Evaluation Time: 1.00000000 years
Nuclide Detail of Doses
=======================
[mrem]
Source: 1
Nuclide Receptor Total
1
ZN-65 5.06E+00 5.06E+00
** RESRAD-BUILD Dose Program Output, Version 3.50 07/20/16 10:15:55 Page: 13 **
Title : Zn-65
Input File : site1.bld
Full Summary
================================================
================================================
=== ===
=== RESRAD-BUILD Dose (Time) Tables ===
=== ===
================================================
================================================
Receptor Dose Received for the Exposure Duration
================================================
(mrem)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.44E+01 5.06E+00
Receptor Dose/Yr Averaged Over Exposure Duration
================================================
(mrem/yr)
Evaluation Time [yr]
0.00E+00 1.00E+00
— — — — — — — — — — — — — — — —
1 2.44E+01 5.07E+00
Attachment 4 MicroShield MDC Model
MicroShield 8.03Ameriphysics (8.03-0000)
Date By Checked
Filename Run Date Run Time DurationCase1 August 5, 2016 10:36:09 AM 00:00:00
Project InfoCase Title CH St. Louis
Description Volumetric ActivationGeometry 8 - Cylinder Volume - End Shields
Source DimensionsHeight 15.0 cm (5.9 in)Radius 28.0 cm (11.0 in)
Dose PointsA X Y Z#1 0.0 cm (0 in) 25.0 cm (9.8 in) 0.0 cm (0 in)
ShieldsShield N Dimension Material DensitySource 3.69e+04 cm³ Concrete 2.35Air Gap Air 0.00122
Source Input: Grouping Method - Standard IndicesNumber of Groups: 25
Lower Energy Cutoff: 0.015Photons < 0.015: Included
Library: GroveNuclide Ci Bq µCi/cm³ Bq/cm³Co-60 1.3800e-006 5.1060e+004 3.7353e-005 1.3820e+000Cs-134 1.6800e-007 6.2160e+003 4.5473e-006 1.6825e-001Eu-152 3.7500e-006 1.3875e+005 1.0150e-004 3.7556e+000Eu-154 3.8300e-007 1.4171e+004 1.0367e-005 3.8357e-001Mn-54 1.0900e-007 4.0330e+003 2.9503e-006 1.0916e-001Sc-46 6.8700e-008 2.5419e+003 1.8595e-006 6.8802e-002Zn-65 8.9400e-008 3.3078e+003 2.4198e-006 8.9533e-002
Buildup: The material reference is SourceIntegration Parameters
Radial 20Circumferential 10
Y Direction (axial) 10
Results
Energy (MeV) Activity (Photons/sec)Fluence RateMeV/cm²/secNo Buildup
Fluence RateMeV/cm²/secWith Buildup
Exposure RatemR/hr
No Buildup
Exposure RatemR/hr
With Buildup
Page 1 of 2Case Summary of CH St. Louis
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0.015 2.450e+04 1.612e-04 1.662e-04 1.382e-05 1.426e-050.03 3.791e+01 3.777e-06 4.440e-06 3.744e-08 4.401e-080.04 8.499e+04 2.257e-02 3.131e-02 9.981e-05 1.385e-040.05 2.126e+04 1.090e-02 1.789e-02 2.904e-05 4.765e-050.1 4.518e+04 9.682e-02 2.629e-01 1.481e-04 4.022e-040.2 1.137e+04 6.502e-02 1.804e-01 1.147e-04 3.183e-040.3 3.752e+04 3.695e-01 9.334e-01 7.010e-04 1.771e-030.4 8.820e+03 1.279e-01 2.970e-01 2.492e-04 5.787e-040.5 9.977e+02 1.957e-02 4.246e-02 3.841e-05 8.335e-050.6 1.458e+04 3.663e-01 7.489e-01 7.149e-04 1.462e-030.8 4.266e+04 1.585e+00 2.965e+00 3.015e-03 5.640e-031.0 1.192e+05 6.006e+00 1.053e+01 1.107e-02 1.941e-021.5 8.897e+04 7.777e+00 1.220e+01 1.308e-02 2.053e-022.0 3.050e-04 3.911e-08 5.752e-08 6.049e-11 8.895e-11
Totals 5.001e+05 1.645e+01 2.821e+01 2.928e-02 5.040e-02
Page 2 of 2Case Summary of CH St. Louis
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