Target Submission Number: TS-Tgt-18-0118_01).pdf · document-proposal, it should be stated that the...

Target Submission Number: TS-Tgt-18-01

C-A-OPM ATT 9.1.15.a of 70 Revision 03

July 15, 2016

If you are using a printed copy of this procedure, and not the on-screen version, then you MUST

make sure the dates at the bottom of the printed copy and the on-screen version match.

The on-screen version of the Collider-Accelerator Department Procedure is the Official Version.

Hard copies of all signed, official, C-A Operating Procedures are available by contacting the

ESSHQ Procedures Coordinator, Bldg. 911A

C-A OPERATIONS PROCEDURES MANUAL

9.1.15.a BLIP Target and Canning Record

Hand Processed Changes

HPC No.

Date

Page Nos.

Initials

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Approved: ___________Signature with Date on File________________

Collider-Accelerator Department Chairman Date

D. Beavis



July 15, 2016

Note 1: Uncontrolled copy printed from electronic master that is valid at time of printing.

Always check that you have the latest revision of this document before use.

Note2: Leave no blanks. Indicate ‘Not Applicable (N/A)’, where appropriate.

Title and Preparer

RaDIATE Material Irradiation at 181 MeV


N. Simos

Instructions

Description Page No.

1. Overview [short summary of purpose of experiment; name of principle

investigator and researcher involved]

4-6

2. Target Material and Properties – [Provide physical properties of each

component/material to be irradiated]

7-12

3. Target Canning Process – [provide images or drawings and reference the

OPM procedures for closing and opening of target can]

13

4. Beam Characteristics [define required beam on target and total current

required]

14

5. Proposed Experiment

[Provide general description of a) how target will be supplied BLIP, b) target

array in box 1 and box 2; c) thermal analysis of target material and target can

d) transport of irradiated target to TPL; target opening and processing at TPL

and e) disposal of waste.

14-25

a. Procedure for Irradiation of Target Material BLIP [summarize steps

for experiment including specialist and contact hours required for task]

15

b. Target Array

[define proposed target array for box 1 and box 2 including calculated

entry and exit energy for each layer. Provide physical dimension of

degraders, target can, materials and water gaps. Provide total water gap

for the array]

15



July 15, 2016

c. Thermal Analysis of Target Materials and Target Can

[provide full description of data to specialist for calculations and any

assumption made on material for calculations]

19

d. Transport and Processing at TPL

[provide description of task involved if different from C-AD OPM 19.17.30

BLIP Target Transfer Procedure]

19

e. Disposal of waste

[describe waste to be generated and how it will be disposed of]

25

6. Activation Analysis of Target Material and Can

[provide list of radionuclide produced and their quantities, references used

for calculations at the time points of:

end of bombardment (EOB)

1 hour after EOB and at the

time of transport to TPL]

25

7. Expected Dose Rate (e.g., R/h at 1 m)

[provide expected dose rate using Microshield or equivalent calculations for

the combined and separate target and can irradiated. Provide expected dose

rate at EOB at BLIP, 1 h after EOB and expected dose rate at the time of

transfer to TPL. Provide decay profiles if the dose rates exceeds limits set up

in applicable RWP for removal from BLIP hot-cell. Attach analyses if any]

31

8. Additional Safety Requirements:

[provide list of isotopes for monitoring in Blip target cooling water in case of

target leak/failure

visual inspection schedule

impact on BLIP air emissions if water gap exceeds historical values

hazardous issues related to volatiles and or corrosive materials used

hazardous materials information must be submitted to the C-AD ESRC]

31

9. Special Operating Instructions and List of References or Supporting

Documents

31

10. Appendix 1: Target Array and Energy Propagation Calculations

Appendix 2: Target Array Loading Table (LT)

[provide additional supporting information as required]

32-33



July 15, 2016

1. Overview

2018 RUN - RAdiATE Experiment at 181 MeV

We propose to continue the irradiation of an array consisting of materials that are of interest to a number

of accelerator facilities around the world and are part of the RaDiATE collaboration for five (5) weeks in

total at 181 MeV and 165 µA. The proposed array has already received beam during the 2017 RUN, but

due to technical issues with the BNL Linac that led to scheduling conflicts with the other active programs,

did not reach the required proton fluence for the study. The 2018 RUN array is identical to the one

already exposed with the only difference the swapping of a target capsule (Silicon capsule of interest to

CERN) with an “equivalent” capsule also provided by CERN. While it will be explained further in the

document-proposal, it should be stated that the target array consisting of six hermetically sealed capsules

survived the increased proton beam intensity showing no signs of degradation at BLIP during the 2017

exposure for the total of ~3.5 weeks proving that the design, layout and predictions of the thermo-

mechanical response were proper.

It should also be pointed out upfront that every measure has been taken into consideration for this

irradiation campaign (as in all previous studies and in particular the 2017 phase of the present study) that

there will be no effect on the isotope production downstream of the inserted array which is placed in

Position #1 of the target station configuration at BLIP. Specifically, the proposed RADiATE array is

placed upstream of the isotope production array which during the irradiation experiment occupies the

downstream position (#2) while the proton energy is increased to 181 MeV. During the irradiation

experiment, the beam energy degrades in the RADiATE array down to the proper energy typically

required by the isotope array while keeping the same beam profile.

The institutions involved (besides BNL) are:

From the US: Fermi National Laboratory, FRIB, PNNL and Los Alamos National Laboratory

International Institutes participating in the experiment: CERN, European Spallation Source (ESS), J-

PARC (Japan), Rutherford-Appleton Laboratory (UK)

To meet the study goals the 2018 RUN will require five (5) weeks of irradiation.

Following irradiation at BLIP and cooling time sufficient for transport to Building 801 hot cells, the target

array will be transported to the TPL hot cells by standard procedures. In the hot cell the target capsules

will be opened, the enclosed specimens will be removed.

Of primary interest for the 181-MeV proton irradiation and for fluences reaching 6.0 1020 p/cm2 will be

the changes induced on key physio-mechanical properties that include (a) resistivity, (b) thermal

conductivity, (c) dimensional changes and thermal expansion, (d) stress-strain behaviour and ductility loss

and (e) thermal annealing characteristics, all crucial parameters for the various test materials considered

for the various applications.

The research array will consist of six capsules in the path of the proton beam along with a vacuum

degrader in the 7th position. The role of the vacuum degrader will be two-fold; one to displace cooling

water from the path of the beam and the second to provide final adjustment of the proton energy so the

isotope producing targets placed in the box downstream will see the same energy as when they normally

operate at the 118 MeV mode.



July 15, 2016

The 5-week irradiation will include the following six capsules in series designated by the contents:

1. Beryllium Capsule (Fermilab)

2. Graphite Capsule (Fermilab) containing 3 graphite grades and a layer of 3D carbon fibre composite)

3. Si Capsule (CERN) containing Si, CfC with micro-coating of Mo, Molybdenum Graphite compound

with Mo coating and Ta-2.5W alloy in an array where all layers are separated by a layer of SIGRAFLEX

graphite for heat conduction

4. Aluminum Capsule (European Spallation Source, ESS) – containing two layers of Aluminum grades

AL6061-T6 and AL57540-O

5. Titanium Capsule (Fermilab-FRIB) – Containing several layers of Ti6Al4V

6. Titanium capsule with several grades of Ti

Figure 1.1 depicts the array configuration of the proposed irradiation

Figure 1:1: Layout cross-section of target capsules/layers in Box1 of BLIP for 2018 RUN Irradiation



July 15, 2016

At the end of the 5-week irradiation the capsules of the array will remain within the BLIP hot cell for a

specified period (calculated on the basis of transport dose limits) and will be transported to the TPL/66C

hot cells for an appropriate decay period. The capsules, as a whole and un-opened, will be transported to

PNNL for opening and post-irradiation analysis. Detailed calculations of the dose, activity and transport

shielding have been performed and listed in the document. Upon decay below transport limits certain of

the capsules will be transported as a whole (un-opened) using certified transport casks to different

laboratory destinations. Specifically,

All un-opened capsules except for Capsule #4 (ESS Aluminum Capsule) will be transported to PNNL;

Aluminum Capsule (#4) will be transported to Los Alamos National Lab.

Summary

It should be stressed that following all the relevant analyses (beam transport, energy

deposition, thermal analyses and heat flux estimations as well as thermos-mechanical

response and safety assessment, dose and activity, there appears to be NO ISSUES

unresolved or areas of concern.

This has been confirmed by the exposure to beam at BLIP of the almost identical array in

2017 RUN where no issues have been detected. This represents the best possible

confirmation of the safety assessment of the proposed experiment.

The slight modification of the array by swapping the CERN Si (position 3) capsule with the

new one which contains Ta2.W alloy has been assessed by the analyses to not introduce any

concerns. The safety driver or the capsule that experiences the highest thermal loads is the

Ti6Al4V capsule #5 which underwent irradiation in 2017 and performed safely.



July 15, 2016

Target Capsule – Be-Fermilab

Target Name: FNAL_Be Target & Canning No.

Assign unique no. (2018-001)

Target Material Properties (Beryllium)

Purity or Grade 99.95%

Chemical Formula Be

Physical Characteristics at

70 oF or 21 oC

Grey metal, odorless, tasteless

Physical Form Foil yes Powder no

Diameter

(inches/mm)

2.375/60.325 Pressed

(Torr)

n/a

Elements (%) Be

Melting Point 1287 oC oF

Boiling Point 2468 oC oF

Thermal Conductivity 200 W.m-1.K-1 Temperature

dependence

(if available) n/a

Density 1.85 g/cm3 g/cm3

Specific Heat 1107 J/kg.K

Target Material Reactions / Properties

Does the Target material

react with any of the

following?

Aluminium no Air no CO2 no

H2O insoluble Lead no Zinc no

Inconel 600 no S/Steel no Copper no

Canning Material Properties

Chemical Formula 304 Stainless Steel

Can Wall Thickness (inches/mm) 0.009/0.2286

Can Dimensions (inches/mm) Can Diameter 2.75/69.9 Can Width 0.333/8.4572

Melting Point 1424 oC 2600 oF

Thermal Conductivity 16.2 W.m-1.K-1

Temperature

dependence

(if available) 16.2@1000C,

21.4@5000C

Density 8 g/cm3




July 15, 2016

Target Capsule #2: Graphite_Fermilab

Target Name: FNAL_Gr Target & Canning No.


Target Material Properties (Graphite grades and Carbon-fibre composite)


Chemical Formula GR 3DCC (three dimensional carbon-carbon composite)


70 oF or 21 oC

Black, odorless, tasteless


Diameter

(inches/mm)

2.375/60.325 Pressed

(Torr)

n/a

Elements (%) Graphite (Carbon)

Melting Point N/A oC oF

Boiling Point N/A oC oF


dependence

(if available) n/a

Density Range 1.0-2.1(different layers) g/cm3





following?





Chemical Formula 304 Stainless





Temperature

dependence


21.4@5000C

Density 8.0 g/cm3




July 15, 2016

Target Capsule #4 – Aluminum_ESS

Target Name: ESS_Alu Target & Canning No.


Target Material Properties (Aluminum)


Chemical Formula Al6061-T6; Al5754-0


70 oF or 21 oC

Grey to black metal, odorless, tasteless


Diameter

(inches/mm)

2.375/60.325 Pressed

(Torr)

n/a

Elements (%)


Boiling Point oC oF


dependence

(if available) n/a






following?










Temperature

dependence


21.4@5000C

Density 8 g/cm3




July 15, 2016

Target Capsule #5&#6 – Titanium_Fermilab

Target Name: FNAL_Ti Target & Canning No.

Assign unique no. (2018-005/006)

Target Material Properties (Ti6Al4V)


Chemical Formula Ti6Al4V


70 oF or 21 oC

Grey to black metal, odorless, tasteless


Diameter

(inches/mm)

2.375/60.325 Pressed

(Torr)

n/a

Elements (%) 6% Al, 4% C=Vanadium, balance Ti


Boiling Point oC oF

Thermal Conductivity 7.1 W.m-1.K-1 Temperature

dependence

(if available) n/a






following?










Temperature

dependence


21.4@5000C

Density 8 g/cm3




July 15, 2016

Target Capsule #3 – Si_CERN (newCERN capsule)

Target Name: CERN_Si Target & Canning No.


Target Material Properties (TZM-Iridium-CuCrCz-Graphite)


Chemical Formula TZM (Mo); Ir; CuCrZr; Graphite

Phys. Characteristics (70oF/21oC) Grey to black metal, odorless, tasteless


Diameter

(inches/mm)

2.375/60.325 Pressed

(Torr)

n/a

Elements (%) (Mo-MoGR):Mo 13.215%, 86.785% Carbon, Si, Carbon


Boiling Point oC oF

Thermal Conductivity

W.m-1.K-1

Graphite= 450

Ta2.5W =54

Si= 84

Mo-CfC= 490

MoMoGR=320

Temp.

dependence

(if available) n/a

Density Flex. Graphite = 0.85;

Ta2.5W = 16.7

Si=8.9;

Mo-CfC= 1.8; Mo-MoGR= 2.5

g/cm3

Specific Heat Mo-MoGR:574; CfC:420;

Ta2.5W:140; S:710

J/kg.K




following?










Temperature

dependence


21.4@5000C

Density 8 g/cm3




July 15, 2016

Target Capsule #7: Vacuum Degrader

Target Name: Degrader_Phase1 Target & Canning No.


Target Material Properties (N/A)


Chemical Formula

Phys. Characteristics (70oF/21oC) VACUUM


Diameter

(inches/mm)

2.375/60.325 Pressed

(Torr)

n/a

Elements (%) N/A

Melting Point oC oF

Boiling Point oC oF

Thermal Conductivity Temperature

dependence

(if available) n/a

Density g/cm3

Specific Heat J/kg.K




following?





Chemical Formula 304 Stainless

Can Wall Thickness (inches/mm) 0.6096/0.024 Upstream and 0.7874/0.031 Downstream




Temperature

dependence


21.4@5000C

Density 8.0 g/cm3




July 15, 2016

3. Target Canning Process

General considerations:

The target capsules or cans containing the Beryllium, Graphite, Si-Ta2.5W-CfC-MoGR, Aluminum and

Titanium as well as the vacuum degrader are made with 304 and/or 316 stainless steels and it are similar

in design with the target cans used for the rubidium chloride targets. The capsule holder design is also

similar to the holders used for the rubidium chloride targets.

Each capsule consists of three parts, the outer rim and the two windows which are welded either under

vacuum or under inert gas (argon) at the outside company EB Industries used for all the isotope-

producing target fabrication.

The window thickness varies between capsules. Specifically, the following thicknesses are used:

Beryllium capsule (#1) : Window thickness = 0.009” 304 stainless

Graphite capsule (#2) : Window thickness = 0.009” 304 stainless

CERN Si (new)capsule (#3) : Window thickness = 0.01181” 316 stainless

Aluminum capsule (#4) : Window thickness = 0.00984” 304 stainless

Titanium capsule (#5) : Window thickness = 0.009” 304 stainless

Titanium capsule #2 (#6) : Window thickness = 0.009” 304 stainless

Vacuum Degrader (#7) : Window thickness = 0.024/0.031” 304 stainless (upstream and

downstream window thicknesses in Vacuum degrader)

TOTAL Width of capsules:

Beryllium capsule #1 width (in/mm): 0.333/8.4572

Graphite capsule #2 width (in/mm) : 0.2345/5.9572

CERN capsule #3 width (in/mm) : 0.20866/5.300

Aluminum capsule #4 width (in/mm): 0.09842/2.500

Ti6Al4V capsule #5 width (in/mm) : 0.2247/5.7072

Ti6Al4V capsule #6 width (in/mm) : 0.0869/2.2072

Vacuum Degrader width (in/mm) : 0.9836/2.4985

Canning Process:

1. The back window of the target capsule is welded onto the capsule rim

2. The solid specimens of each target material type are arranged in a tight and specific arrangement

(see attached Figure ) within the volume of the capsule

3. The target capsule containing the target material is sent to the vendor (EB Industries) where the

front window is welded under vacuum.

4. Vacuum leak tests are performed at the vendor prior to being shipped back to BNL and also at the

BNL shops upon arrival.

The fabricated and leak checked target capsules are given to the BLIP staff along with

instructions of the layout into the irradiation target box. The layout of the array is based on

precise proton beam degradation calculations.



July 15, 2016

4. Beam Characteristics

Beam pattern

(rastered/focused)

Rastered

Incident Linac Energy 181 MeV

Energy on Target

Material

176 MeV

Maximum

Instantaneous Current

permitted

165 µA

Average Current

Desired

140-165 μA

Total Integrated charge

Desired

215,000 (181 MeV) μA - hrs

5. Experiment Description



July 15, 2016

5.a Procedure for irradiation of target material in BLIP:

BLIP staff shall install and remove target array and degraders in BLIP, as per CAD OPM 19.4.5.2.

Irradiations are planned for a total of 5 weeks at 181 MeV.

5.b Target array in Box 1 (upstream) and Box 2 (downstream):

181 MeV Irradiation: Beryllium capsule (position 1), Graphite capsule (positions 2), Silicon

capsule (position 3), Aluminum capsule (position 4), Titanium capsule (position 5), Titanium

capsule #2 (position 6) and Vacuum Degrader #2 (position 7) in Box 1, cGMP approved

RbCl array in Box 2 with 0.220 inch Cu beamstop

See Appendix 1 for details of energy loss in these arrays.

Figure 5.1: Array layout for 2018 RUN irradiation



July 15, 2016

Figure 5.2: Modelling details implemented in FLUKA to help the beam energy degradation estimation

Figure 5.3: Details of a layer within the CERN new Si capsule (position #3) depicting the peripheral

filler space made of graphite. The miss-match in energy loss in the event the beam steers away from its

normal rastering envelope and impacts the edges, is compensated by the introduction of stainless steel of

the same shape of appropriate thickness (selected such that energy loss will be the same) integrated into

the volume of the Vacuum degrader (right)



July 15, 2016

Figure 5.4: Details of TEM specimens (plan view left. cross view right) in ESS aluminum capsule. TEM

specimens selected such that energy degradation is the same throughout the capsule

Capsule content details are listed in Appendix 4.

Figure 5.5: Proton profile throughout the arrays in Box1 and Box2 (Please note that horizontal and left

vertical axes units are centimetres)



July 15, 2016

Figure 5.6: Energy Deposition profile (Please note that horizontal and left vertical axes units are

centimetres)

Figure 5.7: Neutron profile (Please note that horizontal and left vertical axes units are centimetres)

5.c Thermal analysis of target material and target can (attach analyses if any):

See Appendix 4. No issues.



July 15, 2016

5.d Transport of irradiated target to TPL, target opening and processing:

Shown in Figures 5.8 (a; b; c and d) are estimates of dose following the 2018 5-week irradiation

completion. The BLIP hot cell shielding walls have been modelled precisely in an effort to estimate the

dose on the outer wall where the operator stands during removal of the targets from beam and during

placement of the array into the transport cask. Clearly there is no dose registered on the outside surface of

the BLIP hot cell wall due to the RADiATE array.

(a)



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(b)

(c)



July 15, 2016

(d)

Figure 5.8: DOSE at the BLIP Hot Cell (cross section at the Hot Cell Pb Glass Window) following 5-

week irradiation of the 2018 Array for EOB, 1-hour, 2-hours and 12-hours. As noted there is no dose

detectable on the outside of BLIP hot cell where the operator stands even at EOB. Please note that

horizontal and left vertical axes units are centimetres.

Following irradiation, the target capsules will be transported to the TPL hot cells by BLIP staff as per

CAD OPM 19.4.5.3 where it will remain for cooldown and transported to PNNL. At the end of this

cooing period provisions, discussed later in the section, are being made for the entire capsule to be

transported with a CROFT-type shipping cask to PNNL. Detail calculations and analysis have been

performed to assess the dose levels outside the shipping cask (required to be 200≤ mR/hour on contact on

the outside surface of the cask) and the activity/isotopes at the time of shipping. These data are listed in

Appendix 5.

(a)



July 15, 2016

(b)

Figure 5.9: Detailed design of the BLIP Transport Cask (pig) that is used to transport the targets from

BLIP to TPL

(a)



July 15, 2016

(b)

Figure 5.10: Dose within and outside the BLIP Transport cask containing only the new CERN capsule

(which contains the alloy of Tantalum-Tungsten and the molybdenum coated CfC and MoGR). As noted

the transport of the new CERN capsule alone can take place immediately after EOB. Please note that

horizontal and left vertical axes units are centimetres.

a-EOB



July 15, 2016

b-24hr

c-one week

Figure 5.11: Dose within and outside the BLIP Transport cask containing ALL six capsules of the 2018

RUN. Please note that horizontal and left vertical axes units are centimetres.

Shipping target capsules to TPL with the special shipping containers (pigs) will be performed by TPL

staff. Dose measurements at cask exterior will be measured. Store containers in storage vault until the

exterior contact dose is <200mR/h.



July 15, 2016

5.e Disposal of waste:

Stainless steel target body for Graphite and Titanium 1&2 capsules and will be disposed with other target

bodies as solid non-compactable waste as per CAD OPM 19.3.5.6 & 19.3.5.7. No need for disposal of

any of the capsules. All will be shipped whole to other laboratories for post-irradiation examination.

6. Activation Analysis of Target Material and Can

Activation of the target array configuration for the 2018 Irradiation been performed while ignoring

whatever residual activity still remains within the capsules that are being re-introduced from the 2017

irradiation campaign. This stems from the fact that these capsules (beryllium, graphite, aluminium and

Ti6Al4V) have been decaying for over 6 months leading to very small residual activity.

The 2018 campaign includes two (2) new capsules that are taking the place of two equivalent capsules in

the 2017 array layout. These include the new CERN capsule in position 3 (taking the place of the 2017

CERN Si capsule) and the new Ti capsule in position 6 taking the place of a very similar Ti capsule used

in the 2017 campaign.

All estimates were made using the capabilities of the FLUKA transport code and the development of 3D

models that replicate the exact configuration of the irradiation space at BLIP as well as the structural

details of the capsules and their contents. Given that the activity in each capsule and its decay is important

due to the fact that the post-irradiation of each will take place at different locations and shipment will be

required, the activity of each capsule has been calculated.

Presented below is the TOTAL activity and its decay in Curies in the six (6) capsules following the

planned 5-week irradiation in the 2018 RUN

TOTAL ACTIVITY in Target Array Following 5-week Irradiation at 165 µA

EOB: 981 Ci

1 Day: 355 Ci

1 week: 168 Ci

2 weeks: 121 Ci

1 Months: 82 Ci

4 Months: 27 Ci

Note that Be, Graphite, ESS_Aluminum and Ti6Al4V-#1 capsules also have residual activity upon start of

the 2018 irradiation but following the more than 6-month decay, the activity levels are insignificant (see

below).

ESS Al Capsule: from 2017RUN irradiation and 6-month decay: 0.3435 Ci

Fermi Lab Ti6Al4V Capsule: from 2017RUN irradiation and 6-month decay: 0.344 Ci

Fermi Lab Be Capsule: from 2017RUN irradiation and 6-month decay: 0.71 Ci

Fermi Lab Graphite Capsule: from 2017RUN irradiation and 6-month decay: 0.397 Ci

Of particular interest in the activity, decay and isotope production is the new CERN capsule (position 3)

that contains several layers of newly introduced materials such as Ta2.5W, molybdenum coated Carbon

fibre composite (Mo-CfC), and molybdenum coated Molybdenum-Carbon compound (Mo_MoGR).

MoGR and CfC have been irradiated and studied before by N. Simos on behalf of CERN. This time these



July 15, 2016

materials are coated with a micro-size layer of molybdenum.

One expects that the highest activity will result from the Ta2.5W layer. Shown below is the activity

produced in the different layers of the new CERN capsule (at EOB and one month decay).

Detailed activity and decay of new CERN Capsule following the 2018 (5-week) RUN

EOB:

Flex Graphite layers (5): 2.18 Ci

Ta2.5W: 170.8 Ci

Si Layer: 1.98 Ci

Mo coated CfC layer: 16.30 Ci

Mo coated MoGR layer: 24.69 Ci

CERN Capsule windows: 24.0 Ci

CERN capsule rim: 0.43 Ci

One-month decay:

Flex Graphite layers (5): 0.675 Ci

Ta2.5W: 7.65 Ci

Si Layer: 0.08 Ci

Mo coated CC layer: 1.265 Ci

Mo coated MoGR layer: 1.624 Ci

CERN Capsule windows: 4.24Ci

CERN capsule rim: 0.23 Ci

Decay Requirements

Decay requirements were estimated for the following aspects of the experiment:

Figure 6.1: Model of large transport pig and configuration used for estimating dose at the outer surface for

transporting the irradiated array (or capsules individually) from BLIP to TPL(left) and dose profile

associated with the transport cask if transporting to TPL of all 6 target capsules takes place immediately

after EOB. Please note that horizontal and left vertical axes units are centimetres.



July 15, 2016

Decay Requirements for Transport:

NO specific decay requirements are needed since transport to TPL of the entire 6-capsule array can be

transported soon after irradiation ends at BLIP (see Fig. 6.1 right)

The dose profile for transport of irradiated target capsules to PNNL or Los Alamos using the CROFT

Type-A cask (see Figure 6.2a) are estimated using FLUKA and following a model that exactly replicates

the CROFT Cask in 3D configuration.

Based on the detailed analysis on the CROFT Type A cask, the entire array (all 6 capsules) can be

transported out of BNL and to PNNL ~ONE MONTH after irradiation completion (see Fig. 6.3c)

The ORNL Type A shipping cask shown in Figure

(a)



July 15, 2016

(b)

(c)

Figure 6.2: CROFT Transport Cask cross-section (a) and corresponding FLUKA Model used to estimate

dose profiles for transport



July 15, 2016



July 15, 2016

Figure 6.3: Dose calculations for CROFT Transport Cask (all 6 capsules)

Detailed list of isotope and corresponding activity as well as decay is presented in Appendix 5

7. Expected Dose Rate

Dose calculations were performed using the FLUKA transport code. The performance of the model

generated to predict dose and activities was verified via a blind test performed at BLIP. The agreement

between the predictions and the actual measurements were within 1-2%.

A detailed design of the CROFT-type transport cask has been implemented into the transport code to

enable estimation of the dose on the outside surface and its evolution with time. This enabled the

determination of the decay time required for shipment of individual capsules to laboratories outside BNL

for post-irradiation analysis of the capsule contents.

Therefore, shipment can be made out of BNL (to PNNL) ONE month after EOB. Transportation from

BLIP hot cells to TPL based on shielding capabilities of the large available pig (similar to those of the

CROFT-type cask) according to the contact dose which is undetectable even after EOB can take place

immediately after completion of irradiation.

8. Additional Safety Requirements

Nuclides released to Blip Target Cooling Water in the unlikely event of target leak/failure

Nuclide Half life E (abundance, %)

Tc-95 61 d 765.82 (94.34)

V-48 16.1 d 983.5 (100)

Sc-46 83.9 d 889.26 (99) 1120.52 (99)



July 15, 2016

Hf-175 70 d 343.4 (86.92%)

9. Special Operating Instructions

Supporting Documentation

References

OPMs 19.2.22, 19.3.5.6, 19.3.5.7, 19.4.5.2, 19.4.5.3.

Drawings D25-M-3186, 3188; 3452; 3453



July 15, 2016

Appendix 1

Target Array and Energy Propagation Calculations

TITLE: RaDIATE Material Irradiation at 181 MeV

Target Array Number: TA Tgt-18-01

Preparer: Medvedev for Simos

Layer Number

Layer Material Density Thickness MeV Energy

deposited inch mm Ei Eout

Layer

number The BLIP Target Stack, 2018 181 MeV Simos targets RbCl density 2.2g/cm**3 P. Pile (DM)

30/10/17 calculations using range lookup tables eloss in Material

density thickness thickness, (MeV)

Material in Beam (g/cm^3) (mm) (inches) KE (MeV in) Range(mm) KE (MeV out)

1 Be window 1.85 0.3048 0.0120 181.00 144.50 180.71 0.29

2 AlBeMet window 2.10 0.3048 0.0120 180.71 129.00 180.42 0.29

3 Beamline window SS 8.00 0.7874 0.0310 180.42 38.94 178.27 2.15

4 water gap 1.00 2.6924 0.1060 178.27 211.00 176.95 1.32

5 box window SS 8.00 0.5080 0.0200 176.95 37.68 175.56 1.39

6 water gap 1.00 2.2850 0.0900 175.56 205.50 174.44 1.12

7 Simos tgt window - SS 8.00 0.2286 0.0090 174.44 36.77 173.81 0.63

8 Beryllium 1.85 8.0000 0.3150 173.81 134.70 167.8 6.02


10 water gap 1.00 2.2850 0.0900 167.14 188.70 165.98 1.16


12 Graphite 1.85 5.5000 0.2165 165.33 112.70 160.7 4.68


14 water gap 1.00 2.2850 0.0900 160.00 174.90 158.80 1.20


16 Flexible graphite (PNG) 0.85 0.1000 0.0039 157.93 226.40 157.80 0.13

17 Ta2.5W 16.70 0.5000 0.0197 157.80 20.39 155.50 2.30


19 Silicon 2.00 1.0000 0.0394 155.40 104.20 154.60 0.80


21 Mo-coated CfC 1.80 1.3500 0.0531 154.50 110.90 153.35 1.15


18 Mo-coated MoGr 2.50 1.3500 0.0531 153.20 73.84 151.50 1.70



21 water gap 1.00 2.2850 0.0900 150.50 157.20 149.26 1.24


23 Aluminum 2.70 2.0000 0.0787 148.56 73.73 146.2 2.36


25 water gap 1.00 2.2850 0.0900 145.50 148.20 144.25 1.25


27 Ti6Al4V 4.429 2.5 0.0984 143.55 46.49 138.90 4.65

28 Ti6Al4V mushroom 4.429 0.25 0.0098 138.90 43.95 138.40 0.50

29 Ti6Al4V 4.429 2.5 0.0984 138.40 43.68 133.70 4.70


31 water gap 1.00 2.2850 0.0900 132.95 126.50 131.61 1.34


33 Ti alloy mozaic (Gr6) 4.48 0.5 0.0197 130.84 39.35 129.80 1.04

34 Ti alloy (B15-3) 4.76 0.1 0.0039 129.80 36.80 129.60 0.20

35 Ti alloy mozaic (B15-3) 4.76 0.5 0.0197 129.60 36.70 128.50 1.10

36 Ti alloy (Gr23Q/Gr23) 4.43 0.15 0.0059 128.50 38.40 128.20 0.30

37 Ti alloy mozaic (Gr23Q/Gr23) 4.43 0.5 0.0197 128.2 38.25 127.20 1.00


39 water gap 1.00 2.2850 0.0900 126.4 115.70 125 1.40

40 VACUUM DEGRADER front Window SS 7.98 0.6096 0.0240 125.00 20.74 122.87 2.13

41 Vacuum 0.00 25.400 1.0000 122.87 0.00

42 VACUUM DEGRADER back Window SS 7.98 0.7874 0.0310 122.87 20.13 120.07 2.80

43 water gap 1.00 8.0718 0.3178 120.07 105.70 114.81 5.26

44 stainless steel exit window Box 1 8.00 0.5080 0.0200 114.81 17.90 112.93 1.88

45 water cooling 1.00 3.8100 0.1500 112.93 94.80 110.34 2.59

46 stainless steel entrance window Box 2 8.00 0.5080 0.0200 110.34 16.71 108.42 1.92

47 water cooling 1.00 5.0800 0.2000 108.42 88.19 104.85 3.57

48 stainless steel vacuum degrader 8.00 1.4732 0.0580 104.85 15.29 98.92 5.93

49 Water gap 1.00 5.0800 0.2000 98.92 74.93 95.10 3.82

50 Inconel 8.43 0.3048 0.0120 95.10 12.20 93.71 1.39

51 RbCl (solid/liquid) 2.20 16.4000 0.6457 93.71 48.26 73.85 19.86

52 Inconel 8.43 0.3048 0.0120 73.85 7.84 72.2 1.66

53 Water 1.00 5.0800 0.2000 72.19 42.66 67.27 4.92

54 Inconel 8.43 0.3048 0.0120 67.27 6.66 65.5 1.77

55 RbCl (solid/liquid) 2.20 12.7000 0.5000 65.50 25.81 44.50 21.00

56 Inconel 8.43 0.3048 0.0120 44.50 3.23 42.0 2.46

57 Water 1.00 5.0800 0.2000 42.04 16.10 34.09 7.95

58 Copper beam stop 8.96 5.5880 0.2200 34.09 2.01 stop 34.09

59 water gap 1 5.08 0.2000 stop stop stop n/a

RSC Approval: Date Approved:



July 15, 2016

Appendix 2

Target Loading Table

Title RaDIATE Material Irradiation at 181 MeV

Target Array Number: TA-tgt-18-01

Preparer: D. Medvedev for N. Simos

Proposed Run Time (e.g. days, hrs.): proposed start Jan 22nd, 2018

Desired Completion Date: 5 weeks total

Requested Beam Energy (MeV): 181 Requested Beam Current (µA): 140-165 as per canning record TGT-18-01

Item Type and stamped ID

(if available)

Layer #’s from

“Target Array and Energy Propagation

Calculations”

Thickness BLIP Operator

(Initial)

Witness

(Initial) inch

Box 1

1 Water gap 6 0.090

2 Beryllium (BE, one notch) 7-9 0.333

3 Water gap 10 0.090

4 Graphite (C, 2 notches) 11-13 0.255


6 New CERN 2018 (3 notches) 15-20 0.209


8 Aluminum (AL, 4 notches) 22-24 0.097


10 Titanium 1 (T1, 5 notches) 26-30 5.707

11 Water gap 31 0.090

12 DS TI2 capsule ( no notches) 32-38 0.110

13 Water gap 39 0.090

14 Vacuum degrader ( ) 40-41 1.055



July 15, 2016

Continued BOX 2 on next page

BOX 2

15 Water gap 43 0.200

16 SS vacuum degrader (BUU) 48 0.654

17 Water gap 49 0.200

18 RbCl-1 50-52 0.670

19 Water gap 53 0.200

20 RbCl-2 54-56 0.524

21 Water gap 57 0.200

22 Cu beam stop (Ni plated) 58 0.220

RSC Approval: Date Approved:



July 15, 2016

Appendix 3

Note: Proton Energy Profile

Figure A1.1 Cross section of the experiment configuration for the 181-MeV irradiation of the RADIATE

array of 2018 BLIP RUN (5-week irradiation)

Fig A3.1: 2018 Array RUN



July 15, 2016

Table A3.1 Proton Energy Profile for RADIATE Array at 181 MeV: 2018 RUN



July 15, 2016

Verification of BEAM uniform (spatially) degradation

Figure A3.2: Model description to test beam uniform degradation



July 15, 2016

Figure A3.3: Analaysis results indicating uniform degradation



July 15, 2016

Appendix 4 - Thermo-mechanical analysis

Analysis Performed on Target Capsules based on

estimated by SRIM/MCNPX/FLUKA energy

deposition estimates. The estimates of the deposited

energy generated by the three (3) different

approaches where in excellent agreement

Analysis performed by N. Simos (included are also

thermal analysis results conducted by Fermilab

and ESS staff on their respective capsules. i.e.

Beryllium, Graphite, Titanium and Aluminum)

Details of the Finite element analysis are

(Thermal-Structural Analysis of RaDiATE Target

Array)

Conditions

Instantaneous Current: 54.0 mA

Pulse Width: 0.000425 sec

Number of protons 1.03e+15 p/sec

Pulse Frequency = 6.667 Hz

181 MeV

2 configurations for the two back-to-

back phases (both at 181 MeV)

100% beam on target

Summary and Conclusions

Six (6) different target capsules are part of the

irradiation array:

Beryllium, Carbon, newCERN (Ta2.5W, Si, Mo-

MoGR, Mo-CfC), Aluminum and Ti6Al4V (two

capsules of different thickness).

The energy deposited on each capsule (maximum

11 MeV proton beam degradation in Ti capsule

located in position #5 including the capsule

stainless windows) is at levels which ensure that

the het flux condition (200 W/m2-K) is

satisfactorily satisfied (values well below 100

W/m2-K) for the all the capsules containing

materials.

Same holds true for the vacuum degrader that is

placed in the 7th position of the array configuration.

The vacuum degrader is similar to the degraders

used at BLIP as part of the isotope array and has

window thicknesses of 0.6096 mm upstream and

0,7874 mm downstream (as dictated by the proton

beam energy degradation calculations). Windows

are made of stainless steel.

Temperatures and thermal stresses in the 304

stainlees steel windows for the capsules and the

degraders are well within the safety envelope



July 15, 2016

The results are attached. Please note one

significant finding, the water flow

through target box 2 is significantly less

than through target box 1.

Summary and Conclusions (cont.) The temperatures and stresses in the materials inside the

capsules depend on the rastering profile. Under the

nominal rastering (per design) a large area is effectively

heated and therefore the temperatures are well within

the safety envelopes.

Details of Thermo-Mechanical Analysis

Overall Summary NO Problems Anticipated

FLUXES (all ) < 200 W/cm2-m

Outer Window surface Temperatures: ALL below fear of boiling

This section contains excerpt results of a comprehensive finite element analysis. It depicts results

for the vacuum degrader and for the Molybdenum target capsule which experiences the highest

thermal loads. More detailed/descriptive analysis results of all target capsules are available and can

be provided upon request.

The array of 3D non-linear thermal, thermos-mechanical and CFD analyses performed consisted

of:

Steady State Thermal Analysis based on detailed energy deposition produced by the FLUKA

code and inserted as heat generation into the materials. The encapsulated materials under vacuum

into the capsules were in contact with the inner surface of the capsule (therefore conductance rather

than conductivity was used in the thermal and thermos-mechanical analysis). The target capsules

and degraders were cooled with the cooling water through the channels. Recent measurements

established the volumetric flow for Box1 where the target array is to be irradiated to be 22 gpm.

Based on the array with the Thorium target in position 1, 34 mm of total water column/gap is

available for the 22 gpm to flow past the targets. The variability of velocity with non-uniform

channels was tested using a CFD model (data shown in this section). Based on these findings and

the heat transfer analysis based on an analytic study, heat transfer film coefficients were generated

and introduced in the analysis. Conservative values of ~6390 W/m2K were used in the thermal

analysis.



July 15, 2016

Figure A6.1 Energy deposition through-out the target arrays in Box1 and Box2

Based on the findings included in the Memo titled “BLIP Cooling Water Flow Rate Measurement”

It was concluded that the volumetric flow is about 22 gpm for target box 1 and 14 gpm for target box

2. The total mass flow into either target box was unaffected by the contents of the other target box.

Analytical Estimation of heat transfer coefficient through the target capsules

Estimation of Reynolds number related to the velocity of flow Uf through the hydraulic diameter

(2.5mm gap between targets),

NRe

= Uf D

e/ν

Where ν is the dynamic viscosity. Estimate Reynold’s number from Nusselt number

NuDe

= 0.023 (Re)

0.8

(Pr)

0.3

where Pr is the Prandtl number

By relating the film coefficient to the Nusselt number NuDe

NuDe

= hf D

e/ k

De = hydraulic diameter

Estimated and utilized hf 6390 W/m2-sec



July 15, 2016

Figure A6.2 Layout of Array of Phase II with the vacuum degrader (right)

Figure A6.3: CFD analysis with channel width variation shows a difference in the velocity and the

temperature of the fluid passing through (that affecting the temperature of the capsule wall)

Alternative Approach of estimating Heat Transfer Coefficients for the Radiate BLIP

Experiment

Alternative estimates of the forced flow heat transfer coefficients were conducted

independently by other participating teams (European Spallation Source) during the course

of designing their own capsule configuration. Described below is the alternative heat

transfer approach used.

– Assumed duct dimension: 60 x 3 mm2

– Assumed water speed: 2.0 feet/s

– Ambient temperature: 300 K



July 15, 2016

• Convective heat transfer: Dittus-Boelter equation

– h: wall heat transfer coefficient W/m2/K

– k: heat conductivity 0.6 W/m/K

– DH: hydraulic diameter 5.7 mm

– μ: dynamic viscosity 2.9e-4 Pa*s

– j: mass flux 600 kg/m2

/s

This alternative approach leads to wall heat transfer coefficient: 5.5e3 W/m2

/s

NOTE: Good agreement between alternative approaches (formulation) in estimating

heat transfer coefficients in the cooling channels between target capsules. This

provides confidence in the estimates of this critical parameter used in the thermo-

mechanical analyses

In the remaining section of this Appendix 4 excerpt results of the comprehensive thermo-

mechanical analyses conducted for the two degraders to be used in the two irradiation

phases and the various capsules. Of primary interest is the estimate of (a) heat flux at the

outer face of the capsule windows in contact with the forced flow, (b) the temperature of

the stainless steel window, (c) the deformation of the thin stainless capsule/degrader

windows, (d) the stresses that develop in the windows and finally € peak temperatures in

the samples contained within the capsules.

Vacuum Degrader of Phase1 Irradiation – 181 MeV Irradiation

The vacuum degrader of Phase I is a typical degrader used at BLIP during several past

irradiation experiments (i.e. 0.012” stainless window walls) without any issues even during

longer irradiations. The only difference during Phase I irradiation with those in the past is

that the nominal current is assumed higher than before (165 uA). However, the rastering

beam mode is expected to compensate for the increase in current and reduce the energy

density deposited in the thin window significantly. Results depicted in Figure A2.4

demonstrate that no thermo-mechanical issues are anticipated.

ℎ = 0.023𝑘

𝐷𝐻 𝑗𝐷𝐻

𝜇 0.8

𝜇𝐶𝑝𝑘

0.33



July 15, 2016

Figure A6.4: Thermo-mechanical study of vacuum degraders

No issues are expected.



July 15, 2016

Figure A2.5: Thermo-mechanical study of vacuum degrader

Thermo-mechanical Analysis of Target Capsules

Capsule #1: Beryllium

Figure A6.6a: Thermal analysis of Be capsule (position #1 in array) based on BNL analysis



July 15, 2016

Figure A6.6b: Thermal analysis of Be capsule (position #1 in array) based on FNAL analysis

Assessment:

Temperature dependent thermal conductivity for Beryllium

Thermal contact conductance ~ 1750 W/m2K

Calculated for Argon atmosphere (Song and Yovanovich, J. Heat Transfer, Vol. 115, p. 533 , 1993)

Heat transfer coefficient on SS windows ~ 6000 W/m2K

Based on 22 GPM water flow through target box

Analytical calculation (Gnielinski Equation for Nu number)

Assumed no heat transfer at radial edge of capsule

Beam current: 165 µ𝐴

Total energy loss: ~ 8.48 MeV (including SS windows)

Total heat deposition in capsule: 1400 W

Peak temperature: ~ 520 °C

Peak heat flux out of SS window ~ 47 W/cm2

Capsule Window Peak Temperature:

Capsule #2: Graphite (Fermilab)

Window Material: Stainless Steel – 0.009” thick



July 15, 2016

Figure A6.7: Thermal analysis of Graphite capsule (position #2 in array) based on FNAL analysis

Assessment:

Temperature dependent thermal conductivity for Glassy Carbon and Graphite

Thermal contact conductance* ~ 400 W/m2K

*Value N. Simos used in previous analyses (agrees well with experience as well)

Literature values range from 200 – 2000 W/m2K




Assumed no heat transfer at radial edge of capsule

Beam current: 165 µ𝐴

Total energy loss TOTAL: ~ 5.64 MeV (including SS windows)



Peak heat flux out of SS window ~ 31 W/cm2 – OK



July 15, 2016

Capsule #3: CERN_Si (position #3 in array) - New

Flexible graphite: 5 layers x 0.1 mm (0.5 mm total)

o One layer between each specimen layers and window interface

Ta2.5W specimens: 1 layer x 0.5 mm (0.5 mm total)

Mo-coated CfC specimens: 1 layer x 1.35 mm (1.35 mm total incl. coating)

Mo coating 5 µm max. thickness

Mo-coated MoGr specimens: 1 layer x 1.35 mm (1.35 mm total incl. coating)

Mo coating 5 µm max. thickness

Pure Si specimens: 1 layer x 1 mm (1 mm total)

SS304L capsule windows: 2 x 0.3 mm (0.6 mm total)

Total capsule thickness: 5.3 mm

Si capsule in Run 1 was 5.6 mm

Upstream Panasonic Graphite Layer Ta2.5 W Layer Si Layer

CfC Layer MoGr Layer Downstream Pan. Graphite

Figure A6.8a: Thermal analysis of Si capsule (position #3 in array)



July 15, 2016

Heat Flux out of CERN new Capsule: ~40 W/cm2

Peak temperature within the capsule: 327 °C (vacuum atmosphere)

ASSESSMENT:

No temperature, melting or excessive deformation concerns

Capsule #4: ESS Aluminum Contents

(Thermal analysis shown performed by ESS)

Capsule Window:

Capsule content thickness along beam (total):

Assessment:

The temperature in the aluminum alloy is below the operational limit of 144 oC.

Maximum temperature in the SS window: 71 oC.

The temperature in the SS window is not sensitive to the gap size in the beam direction.

Heat Flux at capsule window surface << 200 W/m2-K

Capsule #5: Ti6Al4V

Window Material: Stainless Steel – 0.009” thick



July 15, 2016



July 15, 2016

Listed below are results of independent studies on the Ti capsule #5 (Fermilab). This extra

attention is paid to this capsule for it is capsule that absorbs more beam by comparison to the rest

of the capsules in the array (~9.5 MeV of beam is consumed by the Ti6Al4V layers)


Temperature dependent thermal conductivity for Ti6Al4V

Thermal contact conductance ~ 11000 W/m2K (Helium atmosphere)

o Song and Yovanovich, J. Heat Transfer, Vol. 115, p. 533 (1993)



July 15, 2016




No radial heat transfer

Beam current: 165 µ𝑨

Total energy loss: ~ 10.35 MeV (including SS windows)



Assessment:

This represents the only capsule where the temperature of the outside surface of the window may

reach ~479 K locally.

The heat flux at the same window surface remains well below the threshold of 200 W/(m2-s), with

peak value of ~127 W/m2-s

Titanium #2 Capsule (new)

Fig: Layout (cross-section) of Ti-alloy grades in Ti new capsule (Position 6)

Ti-alloy of Capsule #6 Composition - List

Commercially pure Ti (Grade 1 - JIS-1)

Density: 4.51 g/cm3

Ti-5Al-2.5Sn ASTM Grade 6, UNS R54521(ELI)



July 15, 2016

Density: 4.48 g/cm3

UNS R54521 Al(5) C(0.1) Fe(0.5) H(0.02) N(0.05) O(0.2) Sn(2.5) bal Ti

Ti-6Al-4V ASTM Grade 5, UNS R56400 (Gr5UF)

Density: 4.43 g/cm3

UNS 56400 Al(5.5-6.75) C(0.1) Fe(0.4) H(0.015) N(0.05) O(0.2) V(3.5-4.5) bal Ti

Ultrafinegr Al(6.5) V(4.24) O(0.17) N(0.004) bal Ti

Ti-6Al-4V ASTM Grade 23(ELI), UNS R56401 (Gr23Q/Gr23)

Density: 4.43 g/cm3

UNS 56401 Al(6) C(0.1) Fe(0.4) H(0.015) N(0.05) O(0.2) V(4) bal Ti

Ti-15V-3Cr-3Al-3Sn, AMS 4914 (B15-3)

Density: 4.76 g/cm3

AMS Al(2.5-3.5) Cr(2.5-3.5) Fe(0.25) H(0.015) N(0.05) O(0.13) Sn(2.5-3.5) V(14-16) C(0.05) OT (0.4) bal

Ti

THERMAL Analysis:

Ti-Alloy #2 (Position 6) Capsule: Temperature (left) and Flux (right)

Assessment: No ISSUES

Peak temperature ~ 121 °C

Capsule atmosphere: Helium




July 15, 2016

Appendix 5 - Activation analysis of RaDiATE Target Array RADIONUCLIDES FROM 181 MeV IRRADIATION

Please note: Very detailed isotope tables are listed at the end of Appendix 5 for materials contained in the

new CERN capsule (#3) that replaced the CERN_Si capsule of the 2017 Irradiation.

This was prompted by the fact that the new CERN capsule includes new materials in its content such as

Ta2.5W alloy, molybdenum coated Carbon-fiber composite (Mo-CfC) and molybdenum coated

Molybdenum graphite (Mo-MoGR).

Tables 3.1 depict generated isotopes at EOB in all capsules except the new CERN capsule which is

detailed in Table A3.1a

Table A3.2 depicts isotopes and activity ONE month after EOB for all capsules except the CERN new

capsule (#3).

The very detailed isotopic composition and activity for the new materials in the CERN new capsule are

depicted in Table A3.3.

Please note that the isotopes, activity and decay ARE ALL AVAILABLE following the extensive

analyses. It is extremely time consuming to insert them into tables. However, they will all be available by

the time of the safety Review.



July 15, 2016

Table A5.1 Radionuclides and their activity at EOB produced in all the capsules after bombardment with

181 MeV protons for 5 weeks at 165 µA (residual activity from 2017 RUN insignificant)

Isotope Z Activity, Ci Isotope Z Activity, Ci Isotope Z Activity

Beryllium Capsule New CERN Si (cont.) Ti6Al4V Capsule 1 (cont.)

18 9 0.24

7 4 6.2 56 27 0.26

3 1 .39 55 26 0.20

57 28 0.38 55 27 0.176

53 26 0.87 53 26 0.76

52 25 1.08 52 25 0.82

51 24 2.43 51 24 2.5

51 25 0.43

51 25 0.5 ESS Aluminum Capsule 49 24 1.1

49 24 0.83 27 12 0.42 48 23 1.5

48 23 1.01 24 11 1.47 45 22 0.5

47 23 0.47 18 9 1.25 44 21 0.39

44 21 0.4 57 28 0.43 Ti6Al4V Capsule 2

Graphite Capsule 56 27 0.36 49 21 0.11

11 6 48.12 53 26 0.82 49 23 0.07

10 6 0.31 52 25 1.96 48 21 0.34

7 4 8.12 51 24 2.64 48 23 1.18

57 28 0.39 51 25 0.49 47 21 3.2

53 26 0.88 49 24 1.1 47 23 0.57

52 25 1.06 48 23 1.8 46 21 1.4

51 24 2.4 44 22 0.5 45 20 0.12

51 25 0.50 Ti6Al4V Capsule 1 45 22 3.4

49 24 0.825 49 21 0.36 44 21 5.0

48 23 1.07 49 23 0.21 38 17 0.06

47 23 0.44 48 21 1.12 37 18 0.53

44 21 0. 48 23 4.0 32 15 0.1

New CERN Si Capsule 47 21 10.6 18 9 0.07

See Table A3.3a for detailed isotopes

47 23 1.9

56 27 0.20

46 21 4.75 55 26 0.16

45 20 0.41 55 27 0.12

45 22 11.4 53 26 0.56

44 21 16.5 52 25 0.62

38 17 0.2 51 24 1.90

37 18 1.75 49 24 1.23

32 15 0.30 48 23 1.12



July 15, 2016

Table A5.1a Radionuclides at EOB produced in new CERN capsule

Refer to Table A3.3 for details


Flex. Graphite Layers Mo-M0GR Layer

FLEX Graphite Layers 52 25 96 41

11 6 51 24 90 41

7 4 51 25 89 40

49 24 89 41

Ta2.5W Layer

48 23

87 39

182 73 47 23 87 40

180 73 45 22 11 6

179 73 44 21 7 4

179 74 Si Layer

178 73 28 13

178 74 27 12

177 73 24 11

177 74 22 11 Graphite Fillers

18 9 11 6

176 73 17 9 7 4

176 74 15 8

175 72 11 6

175 73

CERN Si Capsule Windows

175 74 47 23

52 25 45 22

51 24 47 21

51 25 Mo-CfC Layer 46 21

49 24 90 41 44 21

48 23 89 40 43 21

47 23 89 41 38 17

44 21 87 39 32 15

87 40 30 15

11 6 86 39 24 11

7 4 86 40 18 9

28 13 83 38 11 6

24 11 82 37

18 9 82 38

57 28 11 6

55 27 10 6

52 25 7 4



July 15, 2016

Table A5.3b Radionuclides and their activity 1-MONTH after EOB produced in all the capsules after

bombardment with 181 MeV protons for 5 weeks at 165 µA (2017 plus 2018 RUNS)


Beryllium Capsule

Ti6Al4V Capsule 1 (cont.)

37

18

1.54

7 4 4.25

3 1 0.39 57 27 0.14

57 27 0.1 56 27 0.29

56 27 0.25 55 26 0.18

55 26 0.170 54 25 0.28

54 25 0.25 51 24 1.5

51 24 1.43 51 25 0.0

51 25 0 ESS Aluminum Capsule 49 23 0.26

49 23 0.3 3 1 ~0 48 23 0.48

48 23 0.4 7 4 ~0 46 21 0.1

47 23 0 22 11 0.13 44 21 ~0

46 21 ~0 58 27 0.15 Ti6Al4V Capsule 2

Graphite Capsule 57 27 <0.1 49 21

3 1 0.14 56 27 0.23 49 23

7 4 5.5 56 28 ~0 48 21

58 27 ~0 55 26 0.2 48 23

57 27 <0.1 55 27 0 47 21

56 27 0.23 54 25 0.25 47 23

55 26 0.17 52 25 ~0 46 21

54 25 0.26 51 24 1.6 45 20

51 24 1.6 49 23 0.34 45 22

49 23 0.26 48 23 0.50 44 21

48 23 0.30 46 21 0.1 38 17

46 21 <0.1 37 18

Ti6Al4V Capsule 32 15

New CERN Capsule 18 9

See separate Table (3.3) 49 23 0.2 56 27

48 21 ~0 55 26

48 23 1.07 55 27

47 21 ~0 53 26

46 21 3.67 52 25

45 20 0.35 51 24

44 21 ~0 49 24

42 19 ~0 48 23



July 15, 2016

Table A5.3a Radionuclides and their activity decay of the Ta2.5W layer in the CERN new capsule



July 15, 2016

Table A5.3b Radionuclides and their activity decay of the Mo-CfC layer in the CERN new capsule



July 15, 2016

Table A5.3c Radionuclides and their activity decay of the Mo-MoGR layer in the CERN new capsule



July 15, 2016

Appendix 6 – Details of Capsule Contents

Beryllium Capsule Position #1

Capsule consists of straight bars in layers and tensile specimen layers. Total material thickness is 8mm.

The stainless steel windows are 0.009” thick.

Figure A6.1: Beryllium capsule contents



July 15, 2016

Graphite Capsule Position #2



July 15, 2016

Figure A6.2: Graphite capsule contents/modelling details

New CERN Capsule Position #3

Figure A6.3: New CERN Si Capsule (Position #3)

Flexible graphite: 5 layers x 0.1 mm (0.5 mm total)

One layer between each specimen layers and window interface

Ta2.5W specimens: 1 layer x 0.5 mm (0.5 mm total)

Mo-coated CfC specimens: 1 layer x 1.35 mm (1.35 mm total incl. coating)

Mo coating 5 µm max thickness

Mo-coated MoGr specimens: 1 layer x 1.35 mm (1.35 mm total incl. coating)

Mo coating 5 µm max thickness

Pure Si specimens: 1 layer x 1 mm (1 mm total)

SS304L windows: 2 x 0.3 mm (0.6 mm total)

Total capsule thickness: 5.3 mm

Si capsule in Run 1 was 5.6 mm

NOTE



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Side/bottom/top outer fillers are graphite. Therefore, energy mask will have to be incorporated in

downstream vacuum degrader to make up for the non-uniform energy degradation

ESS Aluminum Capsule Position #4

Figure A6.4: ESS Aluminum Capsule 4



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FNAL Ti6Al4V Capsule Position #5



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Figure A6.5: FNAL Titanium Capsule 5

FNAL Ti6Al4V Capsule Position #6



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Tensile + microstructural specimens: 3 layers x 0.5 mm (1.5 mm total)

Meso-scale fatigue foils: 1 layer of 0.1 mm + 1 layer of 0.15 mm (0.25 mm total)

SS304L windows: 2 x 0.2286 mm (0.4572 mm total)

Total capsule thickness: 2.2072 mm (same as first DS Ti capsule)

Appendix 7 - Drawings

Drawings of all nine (9) capsule holders (7 for target capsules and 2 for vacuum degraders) including the

two vacuum degrader capsules have been designed by the C-AD design room and have been signed off.

Micro filler layer 1, from left to right: Gr5UF, Gr5UF, Gr6, Gr6, Gr6

Tensile layer 1, from left to right: Gr5UF, Gr5UF, Gr5UF, Gr6, Gr6, Gr6

Meso fatigue 1 (left) B15-3 (Ti-15V-3Cr-3Al-3Sn)



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The Figure below (4.1) depicts the modified design of the baseline holder which is introduced for all the

capsules and the two vacuum degraders to prevent the rotation of the capsule during irradiation.

Drawing A7.1: Capsule Holders (adhering to newest design of holders used at BLIP)



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Drawing A7.2: Blueprint of Vacuum degrader for 2018 run

Target Submission Number: TS-Tgt-18-0118_01).pdf · document-proposal, it should be stated that the...

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