RT-100 Cask Certificate of Compliance Pre-Application MeetingTallied on segmented (10 cm high...
Transcript of RT-100 Cask Certificate of Compliance Pre-Application MeetingTallied on segmented (10 cm high...
September 18, 2012 RT-100 Pre-Application Meeting 1 This information is company confidential and may not be used without written consent of Robatel Technologies.
RT-100 Cask Certificate of Compliance Pre-Application Meeting
September 18, 2012 Open Session Shielding Evaluations Robatel Technologies, LLC Roanoke, VA
September 18, 2012 RT-100 Pre-Application Meeting 2 This information is company confidential and may not be used without written consent of Robatel Technologies.
Agenda
Introductions RT-100 Shield Design Package contents Source Terms Shielding Methodology NCT Shielding Evaluations HAC Shielding Evaluations RT-100 Loading Table Example Conclusions
September 18, 2012 RT-100 Pre-Application Meeting 3 This information is company confidential and may not be used without written consent of Robatel Technologies.
Introductions
Robatel RT-100 Team Robatel Technologies Robatel Industries
NRC
September 18, 2012 RT-100 Pre-Application Meeting 4 This information is company confidential and may not be used without written consent of Robatel Technologies.
RT-100 Shield Design
Cavity - 195.6 cm high, 173 cm diameter Radial Wall – 3 cm steel, 9 cm lead, 3.5 cm steel,
(0.5 cm ceramic paper and 0.5 cm steel thermal shield)
Bottom Wall – 5 cm steel, 7.5 cm lead, 3.3 cm steel Primary Lid – 21 cm steel Secondary Lid – 10 cm steel, 6 cm lead, 1 cm steel Body – 232.4 cm high, 203 cm diameter
September 18, 2012 RT-100 Pre-Application Meeting 5 This information is company confidential and may not be used without written consent of Robatel Technologies.
Package Contents
Resins, filters and reformed resin from nuclear power plant operation
Typical Materials: Polystyrene based resins such as Duralite Activated Charcoal Nylon filter media Zeolite - hydrated aluminosilicates such as Faujasite
Media contaminated with by-product material
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Package Contents
Content limits Content mass: 15,000 lbs (6806 kg) including liners Decay Heat: 200 Watts Activity: 3000 A2 External Dose Rates: 10 CFR 71.51 and 71.71
Individual nuclides limited by activity per gram to ensure compliance
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Sources of Source Terms Data
Gamma Spectra – SCALE 6.0 ORIGEN-S Photon Yield Library, origen.rev02.mpdkxgam.dat
Beta Spectra – ICRU Report 56, Appendix D Bremsstrahlung Photons – MCNP5 mode e p Spontaneous Fission and Alpha-N Spectra from
SCALE 6.0 ORIGEN-S and actinide decay library, origen.rev00.alphdec.data
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Source Terms – Gamma Emitting Nuclides
For gamma emitting nuclides, the shielding approach is generic. Energy dependent responses are computed for each tally and specific nuclide gamma line responses are found by interpolation.
All gamma emitting nuclides in ORIGEN-S database with > 1 day half life (281 nuclides) evaluated.
201 produced external dose rate responses.
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Source Terms – Gamma Emitting Nuclides
2 Meter Tally Energy Dependent Response
0.00E+00
1.00E-02
2.00E-02
3.00E-02
4.00E-02
5.00E-02
6.00E-02
0.5 1.0 1.5 2.0
Resp
onse
(mRe
m/h
r/Ci
)
Energy (MeV)
2m Dose Rate Response NCT, Cask Side, Segment 15 (0.5-2.0 MeV)
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Source Terms – Beta Emitting Nuclides
For beta emitting nuclides, explicit Bremsstrahlung calculations are performed with MCNP5 in mode e p for: Y-90 Sb-124 Cs-137 La-140 Ce-144
Emax > 2 MeV
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Source Terms – Neutron Emitting Nuclides
For the neutron emitting nuclides alpha-n+ spontaneous fission neutrons computed with ORIGEN-S for 1 Ci of the following: Cm-242 Cm-243 Cm-244 Am-241 Pu-238 Pu-239 Pu-240
Pu-242
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Shielding Evaluations – Methodology
MCNP5 Monte Carlo, release 1.41 Computed exterior dose rate (mrem/hr) for 1 Ci of each
energy line or nuclide distributed in the cavity Tallied on segmented (10 cm high segments) cask surface, 2
meters from the vehicle surface and at the cab surface Determined the maximum value on the cask surface, 2
meter surface and cab surface; this defined the dose rate response functions in mrem/hr/curie
Computed responses for the side, top and bottom Utilized ANSI/ANS 6.1.1-1977, Neutron and Gamma Flux-To-
Dose Conversion Factors
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Shielding Evaluations
Analyzed Trailer Vehicle Dimensions 8’ wide 42’ long Cask is centered on trailer and is vertical Distance from cask centerline to cab 29’ 3”
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Shielding Evaluations
Major Conservatisms in Shielding Evaluations Both NCT and HAC evaluations assumed minimal shell,
lead and lid thickness (i.e. nominal – manufacturing tolerance)
Dose rate responses included 2σ Monte Carlo uncertainty NCT 2 meter limit set to 9.5 mrem/hr NCT Cab limit set 1.9 mrem/hr HAC 1 meter limit set to 950 mrem/hr
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RT-100 Shield Model Dimensions
Component Nominal Model
Inner Shell 3.0 2.97
Lead 9.0 8.5
Outer Shell 3.5 3.47
Bottom 5.0 4.97
Bottom Lead 7.5 7.0
Bottom Plate 3.3 3.27
Primary Lid 21.0 20.95
Secondary Lid 17.0 16.95
Secondary Lid Lead 7.5 7.0
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Shielding Evaluations
Nuclide Activity Limits (Max Ci/g) were established by using the NCT and HAC dose rate limits
Definition of Maximum Curies per Gram NCT 2 Meter:
9.5 mrem/hr / Response (mrem/hr/Ci) /Content Mass
NCT at Cab 1.9 mrem/hr / Response (mrem/hr/Ci) /Content Mass
HAC at 1 meter 950 mrem/hr / Response (mrem/hr/Ci) /Content Mass
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Shielding Evaluations
Max. Ci/g addresses non homogeneity . Analysis assumes max. Ci/g is homogenously
distributed throughout the cavity. Resins generally saturate and are uniform in
activity Nylon filter media takes no credit for metal
cartridge and material is filled through the cavity. End user is ultimately responsible for determining
the maximum Curie per gram of their contents.
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Preliminary Shielding Evaluations
Normal Conditions of Transport (NCT) Model Impact limiters in place Impact limiter foam at reduced (35 and 15 lbs/ft3) density Shells, lead and lids at minimal dimensions Baseline analysis assumes uniform source in polystyrene
resin at 0.65 g/cm3, variation in density and composition are evaluated and accounted for in final results.
Cavity filled with resin and uniform cylindrical source, compaction is evaluated
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Preliminary Shielding Evaluations
NCT Model Sensitivity Studies Compaction of resin and source: 10% Resin Density Variation: 0.325 and 1.13 g/cm3 Resin Compositions: Carbon, Nylon and Zeolite
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NCT Shielding Evaluations NCT Model
Upper Impact Limiter
Lower Impact Limiter
Inner Shell
Lead
Outer Shell
Primary Lid
Secondary Lid
Resin
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NCT Shielding Evaluations NCT 10% Compacted Model
Upper Impact Limiter
Lower Impact Limiter
Inner Shell
Lead
Outer Shell
Primary Lid
Secondary Lid
Resin,10% Compacted
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Shielding Evaluations NCT Tally Surfaces
Cask Radial Surfaces
Cask Top Surface
Cask Bottom Surface
2 Meter Surface
2 Meter Surface
Cab Surface
Cab Surface
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Shielding Evaluations Sensitivity Study Results
Compaction results in lower side and top dose rates, but a slight increase (2%) in the bottom
0.65 g/cm3 produces the lowest Max. Ci/g Carbon produced the lowest gamma attenuation. NCT and
HAC polystyrene gamma responses are increased by 1.07, 1.10 and 1.09 for the side, bottom and top, respectively.
Zeolite has the lowest neutron attenuation. NCT and HAC polystyrene neutron responses are increased by 3.10, 2.75 and 5.40 for the side, bottom and top, respectively.
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Shielding Evaluations NCT Dose Rate Response Results (mrem/hr/Ci)
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Shielding Evaluations NCT Dose Rate Response Results (mrem/hr/Ci)
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Shielding Evaluations NCT Dose Rate Response Results (mrem/hr/Ci)
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Shielding Evaluations NCT Max. Ci/g
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Shielding Evaluations NCT Dose Rate Results for Typical Loading
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Shielding Evaluations
Hypothetical Accident Conditions Impact Limiters off For end drop, lead slumps to bottom creating an annular
void at the top. Also includes 1 inch pin puncture in side. Resin compacts and redistributes to top.
For side drop, lead slumps to one side creating a crescent void along the inside of the outer shell. Resin compacts and redistributes to side.
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Shielding Evaluations
Hypothetical Accident Conditions Source and material relocation Bounding Source Conditions End drop- resin and source compacts and relocates to
the top. Side drop- resin and source compress into a hemi-
cylinder next to the side void
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HAC Shielding Evaluations Annular Void and Puncture with Resin Relocation
Annular void, 2.47 cm high
2.54 cm thick Puncture
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HAC Shielding Evaluations Crescent Void with Resin Relocation
Crescent void, 2.32 cm thick
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HAC Shielding Evaluations Tally Surfaces and Detectors
1 Meter Side
1 Meter Bottom
1 Meter Top
1 Meter Ring Detector 1 Meter Point Detector
.
. .
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HAC Shielding Evaluations Tally Surfaces and Detectors
1 Meter Point Detector
1 Meter Bottom
1 Meter Top
1 Meter Point Detector 1 Meter Point Detector
.
.
.
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Shielding Evaluations HAC Results
End drop annular void with relocation to the top produces the most limiting 1 meter dose rate
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Shielding Evaluations HAC Response Results (mrem/hr/Ci)
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Shielding Evaluations HAC Max. Ci/g
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Shielding Evaluations Neutron and Beta/Bremsstrahlung
Beta/Bremsstrahlung: NCT and HAC responses are negligible. NCT < 1E-6 mrem/hr/Ci and HAC < 1E-4 mrem/hr/Ci.
Neutron NCT and HAC responses evaluated and incorporated into results. However, activities are typically low, and the contributions are negligible.
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Shielding Evaluations Loading Table Based on Min of NCT and HAC Responses
User fills In this column with the contents of their package
Based on either NCT or HAC which ever is more limiting
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Shielding Evaluations Loading Table Based on Min of NCT and HAC Responses
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Shielding Evaluations
Conclusions Evaluations show the RT-100 is below NCT and HAC
regulatory limits if max. Ci/g criteria is met. Dose rate responses and max. Ci/g limits for all significant
isotopes will be provided in the SAR.