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Energy deposition, dose rate and activation calculations for the HiRadMat24 and 27 experimentsDavid Horvath – CERN (EN-STI)
SATIF-13, 10.10.2016
Outline
SATIF-13, 10.10.2016
1. The HiRadMat facility
2. HRMT27 experiment
1. Base of the experiment: The AD-Target
2. Experimental setup
3. Energy deposition, dose rate and activation calculations
3. HRMT24 experiment
D. Horvath - HRMT24, 27 2
CERN HiRadMat facility [1]
• High-Radiation to Materials
• Commissioned in 2011
• Proton beam from SPS
• Evaluate high-intensity beam impacts on materials and accelerator components
• Not an irradiation facility
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 3
Outline
SATIF-13, 10.10.2016
1. The HiRadMat facility
2. HRMT27 experiment [2]
1. Base of the experiment: The AD-Target
2. Experimental setup
3. Energy deposition, dose rate and activation calculations
3. HRMT24 experiment
D. Horvath - HRMT24, 27 4
Antiproton production at CERN
• The AD-Target is the antiproton supplier at CERN
• Designed during the 80s with many variations
• With ELENA operation needs to be guaranteed for the next 20 years
• Redesign of the AD-Target is intended
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 5
The AD-Target
Current design:
• Iridium core, ⌀ 3 mm x 55 mm
• Encapsulated in a graphite matrix
• Body made of a titanium alloy
• Water cooled
Why considering a redesign?
• Extreme temperatures and stresses during operation
• Drop in antiproton yield after installing a new target
• Indicates irreversible changes in the core
• (Water cooling is not necessary anymore)
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 6
Motivation and objectives
• Motivation
• Reduce the uncertainties existing in the core material response in the AD-Target
• Asses the material selection for the new AD-Target
• Objectives
• Recreate equivalent extreme conditions (energy density and stresses) as reached in the AD-Target in a controlled environment
• Identify mechanism if failure and limits of materials of interest impacted by proton beams
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 7
Matching conditions
PS
• 26 GeV/c
• ⌀ 3 mm x 55 mm
• 0.5 mm x 1 mm @ 1 σ
• 1.45e13 proton / pulse
SPS
• 440 GeV/c
• ?
• ?
• ?
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 8
Multiple iterations of energy deposition and thermomechanical simulations were performed using FLUKA Monte Carlo particle transport code
Selected parameters
• ⌀ 8 mm x 140 mm
• 1.5 mm x 1.5 mm @ 1 σ
• Max. 1.5e12 proton / pulse
• Length depends on the density of the tested material
• 140 mm: Iridium and Tungsten
• 160 mm: Tantalum
• 240 mm: Molybdenum
• To see the changes in the materials, the beam intensity was ramped
• 8e10, 2.5e11, 5e11, 7.5e11, 1e12, 1.25e12, and 1.5e12 proton / pulse
• Each target was planned to receive 3 pulse at each intensity
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 9
Residual dose rate of the targets
• For planning the post irradiation experiments
• Conservative approximation, 5 pulse per intensity per target
• Indicates it is possible to handle the targets without a hot cell, after reasonable cooling time.
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 10
[mSv/h] 1 week 1 month 2 months 4 months 6 months 1 year
Ir 29.6 5.5 2.2 0.97 0.57 0.17
W 17.9 2.2 1.09 0.52 0.33 0.14
WL10 17.8 2.2 1.1 0.52 0.33 0.14
W + Ta 18.7 2.2 1.2 0.62 0.4 0.17
Ta 18 2 1.1 0.6 0.39 0.17
Mo 9.7 1.7 1.05 0.67 0.49 0.2
TZM 9.7 1.7 1.03 0.66 0.49 0.2
Specific activity, Exemption limit (LE)
• To determine if a material is radioactive in a legal point of view [4]
• Specific activity [MBq/cm3]
• But the limit is determined based on the separate activity of each isotope.
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 11
Rod 1 week 1 month 2 months 4 months 6 months 1 year
Ir 24.2 6.30 2.40 0.993 0.610 0.233
W 12.4 3.28 1.71 0.828 0.537 0.237
Ta 8.90 1.67 0.822 0.433 0.300 0.167
Mo 3.72 0.692 0.434 0.241 0.153 0.057
Specific activity, Exemption limit (LE)
• A LE limit is specified in the law for each isotope
• The limit is based on the number
𝑖
𝑆𝐴𝑖𝐿𝐸𝑖
• If the sum is bigger than 1 -> It is radioactive
• Each rod has to be considered as radioactive
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 12
Rod 1 week 1 month 2 months 4 months 6 months 1 year
Ir 66500 20200 9220 3840 2100 520
W 45500 12800 6130 2270 1200 415
Ta 35000 7820 4120 1800 1120 429
Mo 23800 7350 3980 1750 1040 367
Activity, Authorization threshold (LA)
• To do a destructive analysis, another limit determines the lab can be used. [4]
• Based on the total activity [MBq]
• Similarly as LE, it is based on the activity of each isotope
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 13
Rod 1 week 1 month 2 months 4 months 6 months 1 year
Ir 170 44.3 16.9 6.99 4.29 1.64
W 87.5 23.1 12.0 5.83 3.78 1.67
Ta 71.6 13.4 6.61 3.48 2.41 1.34
Mo 44.9 8.35 5.24 2.91 1.85 0.685
Activity, Authorization threshold (LA)
• A LA limit is specified in the law for each isotope
• The limit is based on the number
𝑖
𝐴𝑖𝐿𝐴𝑖
• If the sum is
• Σ < 100, class C lab can be used
• 100 < Σ < 10000, class B lab has to be used
• 10000 < Σ, class A lab needed
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 14
Rod 1 week 1 month 2 months 4 months 6 months 1 year
Ir 168 78 34 12 8 6
W 184 88 37 11 7 6
Ta 47 24 13 8 7 6
Mo 7 3 2 0.9 0.6 0.2
Residual dose rate of the experiment
• To determine the needed cooling time of the whole tank
• Changes between the simulation and the experiment
• Tank design
• Tested materials
• Different intensities
• The approval for moving the tank from the experiment hall depends on measurements
• More interesting to compare these measurements with a simulation using the final data.
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 15
Final experimental setup
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 16
Engineering model
Simulated model
Target holder
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 17
Residual dose rate of the tank
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 18
• Date of experiment: 13. Nov. 2015• Date of measurement: 19. Jan. 2016• Total of 8.424*1013 proton on target, divided among the 13 targets
• Moving target holder not easy to simulate• Solution: 26 separate simulation merged
Averaged over 1 cmaround the beam line
Measurement and simulation compared
Location Measured Simulation
1. 21 19.9 (2.1%)
2. 17 17.2 (2.7%)
3. 165 161 (3.3%)
4. 6 6.0 (2.9%)
5. 5 4.5 (3.2%)
6. 10 9.1 (3.6%)
7. 21 19.0 (3.5%)
8. 11 11.0 (2.2%)
9. 0.8 1.5 (3.5%)
10. 6 5.0 (3.2%)
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 19
Residual dose rate [μSv/h]Cooling time 68 days
Top view@ beam line
Side view@ beam line
❶
❺
❹
❸❷
❻
❿
❾
❽
❼
Outline
SATIF-13, 10.10.2016
1. The HiRadMat facility
2. HRMT27 experiment
1. Base of the experiment: The AD-Target
2. Experimental setup
3. Energy deposition, dose rate and activation calculations
3. HRMT24 experiment [3]
D. Horvath - HRMT24, 27 20
Introduction
• Collaboration with multiple institutes
• Motivation:
• To design and operate beryllium beam windows and targets in high energy particle accelerator facilities.
• Objectives:
• Explore the failing modes of different beryllium grades
• Identify potential thermal shock limits
• Compare experimental measurements with numerical simulations
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 21
Beryllium samples
• Size:
• Thin disks with thickness between 0.25 mm and 2 mm, 15 mm in diameter
• “Slugs”, 30 mm thick cylinders with 40 mm diameter
• Beryllium grades:
• PF-60, S-65F (VHP), S-200F (VHP), S-200FH (HIP)
• Organized in 4 separate arrays to test each size / grade with different beam intensities.
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 22
Beam parameters
• 440 GeV/c proton beam
• 0.3 mm @ 1 σ
• Intensity: 1.7*1011 proton per bunch
• Bunch distribution:
• Array 1: 144 bunches [9%]
• Array 2: 72 + 216 bunches (5.5 mm separation) [18%]
• Array 3: 24 + 6 x 144 bunches (same axis) [55%]
• Array 4: 288 bunches [18%]
• Total: 1608 bunches – 2.7336*1014 protons
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 23
Simulated geometry
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 24
1
2
3
4
Materials
• Structural elements:Aluminium
• Index plunger:Stainless steel
• Beam windows:Glassy carbon and Duragraph
• Gages
• Strain: Constantan strain gages
• Temperature: Nickel
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 25
Residual dose rate – 2 months cooling
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 26
Residual dose rate of “slugs”
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 27
High contribution from the index plunger and gages.
Maximum residual dose rate along beam
• Maximum:860 μSv/h
• At the tank’s wall:~ 2 μSv/h
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 28
Conclusion
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 29
• FLUKA energy deposition simulation results can be used for thermo-mechanical calculations as input
• FLUKA activation simulations can be effectively used
• To plan the cooling times for irradiation experiments
• To determine if a material has to be considered as radioactive
• To select the necessary laboratory class for destructive work on radioactive materials
• The FLUKA simulation results and the measurements are in good agreement for residual dose rates after irradiation experiments.
References
[1] HiRadMat website: http://n.ch/hiradmat/
[2] C. Torregrosa et.al. “The Hiradmat 27 Experiment: Exploring High-Density Materials Response at Extreme Conditions for Antiproton Production”7th International Particle Accelerator Conference, Busan, Korea, 8 - 13 May 2016, pp.THPMY023https://cds.cern.ch/record/2207471
[3] K. Ammigan et al. “Examination of Beryllium Under Intense High Energy Proton Beam at CERN's HiRadMat Facility”6th International Particle Accelerator Conference, Richmond, VA, USA, 3 -8 May 2015, pp.WEPTY015https://cds.cern.ch/record/2141752
[4] Swiss Federal Council: Radiological Protection Ordinance (StSV)
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 30
Acknowledgements
Marco Calviani and Claudio Torregrosa
Thank you for your attention!
Backup slide
HRMT27 - Targets after the experiment
SATIF-13, 10.10.2016 D. Horvath - HRMT24, 27 34
Ir target after full intensity Impact
Longitudinal cracks in Iridium at intermediate intensities.
W after full intensity
• Tungsten targets present the larger amount of longitudinal cracks.
• Spall of fragments at the surface also took place in tungsten.
IRIDIUM
TUNGSTEN
MOLYBDENUMTANTALUM • No cracks were observed in Ta targets.