LBNF Radiation Safety Issues Overview

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S.D. Reitzner, N. Mokhov, I. Rakhno, I. Tropin, and K. Vaziri
NBI 2022
September 21, 2022
 
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S.D. Reitzner, et. al  | LBNF Radiation Safety Issues
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Beamline Overview
Radiation transport modeling parameters
Prompt radiation
Residual radiation
Ground water protection
Activated air release
Conclusion
 
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Radiological safeguards designs based on 2.4 MW operation
120 GeV protons @ 1.5×10
14
 p / 1.2 s
56% duty factor
Model radiation transport using MARS
-
2.2 m target for target hall calculations
-
1.5 m target for decay pipe and absorber
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Target Station
Absorber Hall
Decay 
Pipe
Target
Hall
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10 mrem/year from
entire lab at site
boundary.
0.25 mrem/hr  for rad
worker
50 
μ
rem/hr for non rad
workers
mrem/hr
166 mrem/hr
7 ft thick ceiling
5 ft thick walls
No access during operation.
Energy (GeV)
Neutrons/GeV/cm
2
/s
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mrem/hr
Nitrogen handling 
room (NHR) 
Pretarget
2.5 mrem/hr
No access in pretarget
or NHR during beam on 
53 mrem/hr
Morgue
86 mrem/hr
Y = 0 m
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y = 4.9 m
Work Cell
Power 
Supply
Radioactivate 
Water (RAW)
54 
μ
rem/hr
Battlement
Borated 
poly cover
mrem/hr
Access 
Corridor
Rad worker access  to
support rooms except RAW
N
2
 fill
Y = 4.9 m
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mrem/hr
200 rem/hr max
t-blocks
<200 mrem/hr top 
of shield pile
800 rem/hr max
cooling panels
230 mrem/hr 
max top of steel
150 mrem/hr max 
on concrete blocks
100-d irr/4-hr cooling
 
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Work cell is designed for 4000 rad/hr on contact object.
2000 R/hr activity estimated for Horn B or Horn A and target
Work cell and morgue located in target hall.
Target hall will be shielded enough to handle unshielded moves.
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Federal surface water
limits:
-
3
H < 2600 pCi/mL
-
22
Na < 16 pCi/mL
Potential transmission
to ground water via
support piles.
-
Shield to meet
groundwater limit.
Groundwater limit below
limit of detection
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H     <1 pCi/mL
-
22
Na  <0.04 pCi/mL
Underdrain system to
reduce buildup.
stars cm
-3
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-1
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Shield to meet
groundwater limit.
Steel kern downstream
to protect from muons
-
170’ length
-
10’ diameter
Barrier to prevent
tritium diffusing from
shielding into
environment.
Monitoring wells to be
used to detect any
contamination.
 
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Air emission permit of 0.1 mrem/year annual sitewide release
(EPA)
-
LBNF annual release goal to be < 30 μrem/year to the public.
Nitrogen cooling for the target hall and decay pipe will maintain
LBNF air releases within budget.
Maintain negative pressure in areas of activated air.
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Tritium from other sources
28.25% of 
FNAL Site 
Limit
Total release:
30.66%  of 
FNAL Site Limit
0.49% FNAL Site Limit
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Appropriate selection of shielding to maintain prompt dose below
limits set by FNAL policy.
-
Model for 120 GeV, 2.4 MW operation.
Shielding and underdrains will be used to maintain concentration
of radioactive isotopes below regulatory limits for surface and
ground water.
Morgue and work cell in target hall to allow for unshielded
moves.
Use of nitrogen for cooling and long transit times in ventilation to
maintain activated air releases below regulatory limit.
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The Long-Baseline Neutrino Facility (LBNF) addresses radiation safety issues through various components such as prompt radiation, residual radiation, activated air release, and ground water protection. Detailed modeling parameters using MARS for radiological safeguards are discussed, along with prompt dose levels at different locations within the facility. The safety measures ensure protection for both radiation and non-radiation workers during operation.

  • Neutrino Facility
  • Radiation Safety
  • Modeling Parameters
  • Prompt Dose
  • Radiological Safeguards

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  1. Long-Baseline Neutrino Facility LBNF LBNF Radiation Safety Issues S.D. Reitzner, N. Mokhov, I. Rakhno, I. Tropin, and K. Vaziri NBI 2022 September 21, 2022

  2. Introduction Beamline Overview Radiation transport modeling parameters Prompt radiation Residual radiation Ground water protection Activated air release Conclusion 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 2 LBNF

  3. LBNF Beamline Components Neutrino Beam to SURF, SD Absorber Complex (LBNF-30) Target Complex (LBNF-20) Primary Beamline Enclosure Decay Region Primary Beam Service Building (LBNF-5) Fermilab Main Injector Tunnel 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 3 LBNF

  4. Radiation Transport Modeling Parameters Radiological safeguards designs based on 2.4 MW operation 120 GeV protons @ 1.5 1014 p / 1.2 s 56% duty factor Model radiation transport using MARS - 2.2 m target for target hall calculations - 1.5 m target for decay pipe and absorber 09.21.22 S.D. Reitzner, et al | LBNF Radiation Safety Issues 4 LBNF

  5. LBNF MARS Model Absorber Hall Target Station Target Hall Decay Pipe 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 5 LBNF

  6. Prompt Dose 7 ft thick ceiling 5 ft thick walls 10 mrem/year from entire lab at site boundary. 166 mrem/hr 0.25 mrem/hr for rad worker 50 rem/hr for non rad workers Neutrons/GeV/cm2/s mrem/hr No access during operation. Energy (GeV) 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 6 LBNF

  7. Prompt Dose at Nitrogen Handling Room Level Y = 0 m 2.5 mrem/hr Nitrogen handling room (NHR) Morgue Pretarget mrem/hr 53 mrem/hr 86 mrem/hr No access in pretarget or NHR during beam on 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 7 LBNF

  8. Prompt Dose at Battlement Level Access Corridor Y = 4.9 m 54 rem/hr Power Supply Radioactivate Water (RAW) N2 fill Borated poly cover mrem/hr Work Cell Battlement Rad worker access to support rooms except RAW y = 4.9 m 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 8 LBNF

  9. Residual Dose <200 mrem/hr top of shield pile 150 mrem/hr max on concrete blocks 230 mrem/hr max top of steel 100-d irr/4-hr cooling mrem/hr 200 rem/hr max t-blocks 800 rem/hr max cooling panels 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 9 LBNF

  10. Remote Handling and Storage Work cell is designed for 4000 rad/hr on contact object. 2000 R/hr activity estimated for Horn B or Horn A and target Work cell and morgue located in target hall. Target hall will be shielded enough to handle unshielded moves. 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 10 LBNF

  11. Ground Water Protection for Target Hall Federal surface water limits: 3H < 2600 pCi/mL - 22Na < 16 pCi/mL Potential transmission to ground water via support piles. - - Shield to meet groundwater limit. Groundwater limit below limit of detection 3H <1 pCi/mL - 22Na <0.04 pCi/mL Underdrain system to reduce buildup. - stars cm-3s-1 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 11 LBNF

  12. Ground Water Protection Absorber Hall Shield to meet groundwater limit. Steel kern downstream to protect from muons - 170 length - 10 diameter Barrier to prevent tritium diffusing from shielding into environment. Monitoring wells to be used to detect any contamination. 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 12 LBNF

  13. Air Activation Air emission permit of 0.1 mrem/year annual sitewide release (EPA) - LBNF annual release goal to be < 30 rem/year to the public. Nitrogen cooling for the target hall and decay pipe will maintain LBNF air releases within budget. Maintain negative pressure in areas of activated air. 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 13 LBNF

  14. Air Release Path 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 14 LBNF

  15. Total Air Releases 3H 11C 13N 15O 41Ar Exit (Ci/yr) 7.08 10-2 2.37 10-4 1.59 10-12 2.23 10-70 Absorber Hall 2.54 1.32 10-4 5.09 10-31 NHR 1.03 1.41 1.36 2.42 102 1.4 101 8.60 10-5 Target Hall 1.16 1.98 2.78 101 1.68 10-1 4.21 10-12 Morgue 1.16 1.29 7.78 10-3 8.77 10-9 9.59 10-1 Primary Encl 1.16 5.53 41Ar from RAW 0.49% FNAL Site Limit 0.96 Ci/yr Tritium from other sources 3H Source Activity (Ci/yr) Total release: 30.66% of FNAL Site Limit Target Pile 540 28.25% of FNAL Site Limit Decay Pipe 152 Absorber Pile 156 Tgt He Cooling 0.015 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 15 LBNF

  16. Wait Time Access Due to Activated Air No access to area until air activity below 0.1 DAC after beam off. DAC: Derived Air Concentration DAC = ??? - Ci = concentration of ith isotope Location Wait Time Absorber Hall 6 hrs NHR 45 min Target Hall 1.5 hrs Primary Encl 1.5 hrs ?? - CRi = concentration of ith isotope which gives 5000 mrem effective dose from a 2000 hr exposure. 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 16 LBNF

  17. Conclusion Appropriate selection of shielding to maintain prompt dose below limits set by FNAL policy. - Model for 120 GeV, 2.4 MW operation. Shielding and underdrains will be used to maintain concentration of radioactive isotopes below regulatory limits for surface and ground water. Morgue and work cell in target hall to allow for unshielded moves. Use of nitrogen for cooling and long transit times in ventilation to maintain activated air releases below regulatory limit. 09.21.22 S.D. Reitzner, et. al | LBNF Radiation Safety Issues 17 LBNF

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