OMEGA
LLE
RADIOLOGICAL CONTROLS
MANUAL
LLEINST 6610F S-AA-M-16
LLEINST 6610F S-AA-M-16
OMEGA
LLE
RADIOLOGICAL CONTROLS
MANUAL
LLEINST 6610F 15 August 2011 LLE INSTRUCTION 6610F SUBJECT: LLE Radiological Controls Manual 1. Purpose: To promulgate the procedures for radiological controls in the
Laboratory for Laser Energetics. 2. Promulgation: The attached LLE Radiological Controls Manual is hereby
promulgated. 3. Approval: Walter T. Shmayda LLE Radiation Safety Officer
LLE NOTICE 1000 15 August 2011
LLE NOTICE 1000 SUBJECT: LLE INSTRUCTION 6610F 1. Purpose: To promulgate LLE Radiological Controls Manual (LLE INST 6610F).
2. Directions:
Remove Pages Replacement Pages
All-6610C All-6610D
All-6610D All-6610E
All-6610E All-6610F
3. Complete Record of Change page i by entering “6610F,” “Entered by,” and
“Date of Entry” columns.
4. Approval: Walter T. Shmayda
LLE Radiation Safety Officer
LLE Radiological Controls Manual RADCONMAN LLEINST 6610F 15 August 2011
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Record of Changes and List of Effective Pages
Record of Changes Change/ Date of Change/ Date of Rev. No. Entered by Entry Rev. No. Entered by Entry
E 5/9/08
F W. Shmayda 8/15/11
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List of Effective Pages
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Change/ Rev.No. Date
i Rev. F 15 August 2011 II-25 Rev. F 15 August 2011 ii Rev. F 15 August 2011 II-26 Rev. F 15 August 2011 iii Rev. F 15 August 2011 III-1 Rev. F 15 August 2011 iv Rev. F 15 August 2011 III-2 Rev. F 15 August 2011 v Rev. F 15 August 2011 III-3 Rev. F 15 August 2011 vi Rev. F 15 August 2011 III-4 Rev. F 15 August 2011 I-1 Rev. F 15 August 2011 III-5 Rev. F 15 August 2011 I-2 Rev. F 15 August 2011 III-6 Rev. F 15 August 2011 I-3 Rev. F 15 August 2011 III-7 Rev. F 15 August 2011 I-4 Rev. F 15 August 2011 III-8 Rev. F 15 August 2011 I-5 Rev. F 15 August 2011 III-9 Rev. F 15 August 2011 I-6 Rev. F 15 August 2011 III-10 Rev. F 15 August 2011 I-7 Rev. F 15 August 2011 III-11 Rev. F 15 August 2011 I-8 Rev. F 15 August 2011 IV-1 Rev. F 15 August 2011 I-9 Rev. F 15 August 2011 IV-2 Rev. F 15 August 2011 I-10 Rev. F 15 August 2011 IV-3 Rev. F 15 August 2011 I-11 Rev. F 15 August 2011 IV-4 Rev. F 15 August 2011 II-1 Rev. F 15 August 2011 IV-5 Rev. F 15 August 2011 II-2 Rev. F 15 August 2011 IV-6 Rev. F 15 August 2011 II-3 Rev. F 15 August 2011 V-1 Rev. F 15 August 2011 II-4 Rev. F 15 August 2011 V-2 Rev. F 15 August 2011 II-5 Rev. F 15 August 2011 V-3 Rev. F 15 August 2011 II-6 Rev. F 15 August 2011 App Map A-1-i Rev. F 15 August 2011 II-7 Rev. F 15 August 2011 App Map A-1-ii Rev. F 15 August 2011 II-8 Rev. F 15 August 2011 App Map A-2a Rev. F 15 August 2011 II-9 Rev. F 15 August 2011 App Map A-2b Rev. F 15 August 2011 II-10 Rev. F 15 August 2011 App Map A-2c Rev. F 15 August 2011 II-11 Rev. F 15 August 2011 App Map A-3a Rev. F 15 August 2011 II-12 Rev. F 15 August 2011 App Map A-3b Rev. F 15 August 2011 II-13 Rev. F 15 August 2011 App Map A-3c Rev. F 15 August 2011 II-14 Rev. F 15 August 2011 App Map A-3d Rev. F 15 August 2011 II-15 Rev. F 15 August 2011 App Map A-4a Rev. F 15 August 2011 II-16 Rev. F 15 August 2011 App Map A-4b Rev. F 15 August 2011 II-17 Rev. F 15 August 2011 App Map A-4c Rev. F 15 August 2011 II-18 Rev. F 15 August 2011 App Map A-4d Rev. F 15 August 2011 II-19 Rev. F 15 August 2011 App Map A-4e Rev. F 15 August 2011 II-20 Rev. F 15 August 2011 App Map A-4f Rev. F 15 August 2011 II-21 Rev. F 15 August 2011 App Map A-4g Rev. F 15 August 2011 II-22 Rev. F 15 August 2011 App Map A-4h Rev. F 15 August 2011 II-23 Rev. F 15 August 2011 App Map A-4i Rev. F 15 August 2011 II-24 Rev. F 15 August 2011 App Map A-4j Rev. F 15 August 2011
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List of Effective Pages
Page No. Change/Rev.
No. Date Page No. Change/Rev.
No. Date App Map A-4k Rev. F 15 August 2011 App Map A-4l Rev. F 15 August 2011 App Map A-4m Rev. F 15 August 2011 App Map A-4n Rev. F 15 August 2011 App Map A-4o Rev. F 15 August 2011 App Map A-4p Rev. F 15 August 2011 App Survey Log A-1
Rev. F 15 August 2011
App Survey Log A-2
Rev. F 15 August 2011
App Survey Log A-3
Rev. F 15 August 2011
App Survey Log A-4
Rev. F 15 August 2011
App Log A-4 Rev. F 15 August 2011 App Log A-5 Rev. F 15 August 2011 App Log A-6 Rev. F 15 August 2011 App Log A-7 Rev. F 15 August 2011 App Form A-1 Rev. F 15 August 2011 App Form A-2 Rev. F 15 August 2011 App Form A-3 Rev. F 15 August 2011 App B-i Rev. F 15 August 2011 App B-ii Rev. F 15 August 2011 App B-iii Rev. F 15 August 2011 App-B-iv Rev. F 15 August 2011 App-B-v Rev. F 15 August 2011 App-B-vi Rev. F 15 August 2011 App-C-i Rev. F 15 August 2011 App-C-ii Rev. F 15 August 2011 App-C-iii Rev. F 15 August 2011
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Table of Contents
Part I: Radiological Control Fundamentals1000 Introduction ................................................................................................................ I-11001 OMEGA Neutron Radiation ..................................................................................... I-21002 OMEGA EP Radiation ............................................................................................... I-31003 Neutron Activation Gamma Radiation ....................................................................... I-41004 Tritium Beta Radiation ............................................................................................... I-51005 Surface Contamination ............................................................................................... I-71006 Airborne Radiation ..................................................................................................... I-71007 Biological Effects of Radiation .................................................................................. I-81008 Radiation Protection Principles .................................................................................. I-91009 Summary of Radiological Limits ............................................................................... I-10
Part II: Radiation Protection Systems2000 OMEGA Shielding System ........................................................................................ II-12001 OMEGA EP Shielding System .................................................................................. II-72002 Tritium Fill Station ..................................................................................................... II-92003 Tritium Transport ....................................................................................................... II-122004 Target Area Tritium Removal Systems ...................................................................... II-132005 Environmental Monitoring System ............................................................................ II-192006 Radiation Detection Instruments ................................................................................ II-22
Part III: Requirements and Procedures3000 Shielding Effectiveness Monitoring ........................................................................... III-13001 Target Chamber Activation Surveys ........................................................................... III-13002 Target Bay General Radiation Surveys ...................................................................... III-23003 Airborne Radiation Surveys ....................................................................................... III-23004 Surface Contamination Surveys ................................................................................. III-33005 Liquid Activity Surveys ............................................................................................. III-43006 Anticontamination Clothing....................................................................................... III-53007 Establishing a Controlled Surface Contamination Area ............................................ III-53008 Target Chamber Entry ................................................................................................ III-63009 Decontamination Procedures ..................................................................................... III-73010 Internal Transfer of Tritium Targets ........................................................................... III-83011 Radioactive Material Accountability and Disposal .................................................... III-83012 LLE Monthly Tritium Inventory ................................................................................ III-103013 Scintillation Counting ................................................................................................ III-103014 Personnel Monitoring ................................................................................................. III-10
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3015 Material with Fixed Activity ...................................................................................... III-113016 Estrablishing a Radioactive Materials Control Area .................................................. III-11
Part IV: Emergency Procedures4000 Spill of Radioactive Material ..................................................................................... IV-24001 High Airborne Activity............................................................................................... IV-34002 Acute Release of Tritium ........................................................................................... IV-44003 UR Security Acute Release of Tritium Emergency Procedure (from LLE Tritium Fill Station) ............................................. IV-6
Part V: Maintenance Procedures5000 Tritium Fill Station Radiological Requirements ........................................................ V-15001 Experimental Operation Radiological Requirements ................................................ V-2
APPENDICESAppendix A: Survey Maps, Logs, and Forms Survey Map A-1—Radiation Shielding Monitoring Points Survey Map A-2a—Target Bay Gamma Radiation—Target Bay Ground
Level Survey Map A-2b—Target Bay Gamma Radiation—TMS Platform Level 1 Survey Map A-2c—Target Bay Gamma Radiation—TMS Platform Level 2 Survey Map A-3a—OMEGA EP Target Bay Gamma Radiation—TAS Platform
Level 1 Survey Map A-3b—OMEGA EP Target Bay Gamma Radiation—TAS Platform
Level 2 Survey Map A-3c—OMEGA EP Target Bay Gamma Radiation—TAS Platform
Level 3 Survey Map A-3d—OMEGA EP Target Bay Gamma Radiation—Laser Bay
Floor Survey Map A-4a—Surface Contamination Survey Log Survey Map A-4b—Surface Contamination Survey Log (LaCave) Survey Map A-4c—Surface Contamination Survey Log (LSC Area) Survey Map A-4d—Surface Contamination Survey Log
(Micro Assembly Lab, Rm. 2828) Survey Map A-4e—Surface Contamination Survey Log (Tritium Facility) Survey Map A-4f—Surface Contamination Survey Log
(OMEGA Target Bay–Ground Level) Survey Map A-4g—Surface Contamination Survey Log
(OMEGA Target Bay—TMS Platform Level 1) Survey Map A-4h—Surface Contamination Survey Log
(OMEGA Target Bay—TMS Platform Level 2) Survey Map A-4i—Surface Contamination Survey Log
(Target Positioner 2) Survey Map A-4j—Surface Contamination Survey Log (LaCave Darkroom) Survey Map A-4k—Surface Contamination Survey Log (LaCave)
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Survey Map A-4l—Surface Contamination Survey Log(Decontamination Area Room 136)
Survey Map A-4m—Surface Contamination Survey Log(Cart Maintenance Room – Room 150A)
Survey Map A-4n—Surface Contamination Survey Log(Pump House/TC-TRS – Room 150B)
Survey Map A-4o—Surface Contamination Survey Log (Room 157 Hood) Survey Map A-4p—Surface Contamination Survey Log
(TC-TRS Condensate Transfer) Survey Log A-1—Surface Contamination Survey Log for Clean Items Survey Log A-2— Surface Contamination Survey Log
Cryo and Tritium Facility Water Condensate Survey Log A-3—Liquid Activity Survey Log Survey Log A-4—Airborne Radiation Survey Log Log A-4—Target Chamber Personnel and Material Entry Log Log A-5—Radioactive Material Control Log Log A-6—Weekly Radiological Survey Cover Sheet—Target Production Log A-7—Weekly Radiological Survey Cover Sheet—Experimental
Operations Group Form A-1—Target Chamber Access Authorization Form A-2—LLE TFS, CTHS, OMEGA Training Inventory Form A-3—Warm Tritium Target Inventory
Appendix B: Definitions
Appendix C: Acronyms & Abbreviations
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LLE RADCONMANLLEINST 6610F
1000 IntroductionRadiological controls include all aspects of ensuring the protection of personnel and the environment from the hazards associated with ionizing radiation and radioactive materials. As a U.S. Nuclear Regulatory Commission agreement state, New York State has accepted the responsibility to establish and enforce regulations governing the handling of radioactive material and radiation-producing devices. The NYS Department of Health governs the licensing of users of radioactive material and the regulations that are applicable to these users, while the NYS Department of Environmental Conservation governs the protection of the environment and general public at large. At the University of Rochester, a Radiation Safety Committee is responsible for establishing the procedures that implement the NYS requirements. These procedures are contained in a UR Radiation Safety Manual. The UR Radiation Safety Unit is responsible for enforcing compliance with these procedures by the users (Principal Investigators) of radioactive material and radiation-producing devices at the University. The Laboratory for Laser Energetics (LLE) is both a user of radioactive material (primarily tritium) and has a device, the OMEGA Laser System, that produces radiation (neutrons and x rays directly and beta-gamma radiation indirectly).
Tritium stored in the LLE Tritium Fill Station is used to fill polymer capsules for inertial confinement fusion (ICF) implosion experiments. Fusion experiments yield high-energy prompt neutron radiation as a result of the fusion process, prompt gamma radiation from neutron capture, and delayed gamma radiation as a result of neutron activation of high-Z structural material.
This manual describes the radiation protection systems in the OMEGA Laser Facility and the radiological control procedures used at LLE to ensure personnel and environmental protection from sources of ionizing radiation. In effect, this manual describes how the requirements of the University of Rochester Radiation Safety Manual are fulfilled at LLE. In the event of a conflict between this manual and the UR Radiation Safety Manual, the UR Radiation Safety Manual takes precedence. See Appendix B for definitions of radiation safety terms.
Part IRadiological Control Fundamentals
1000 Introduction1001 OMEGANeutronRadiation1002 OMEGAEPRadiation1003 NeutronActivationGammaRadiation1004 TritiumBetaRadiation1005 SurfaceContamination1006 AirborneRadiation1007 BiologicalEffectsofRadiation1008 RadiationProtectionPrinciples1009 SummaryofRadiologicalLimits
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1001 OMEGA Neutron RadiationThe fusion of deuterium-tritium (DT) and pure deuterium (DD) produces energetic charged particles, x rays, and neutrons. The basic reactions are as follows:
. %
. %
%
n
P
n
2 45 50
3 02 50
14 100
D D He MeV
D D T MeV
T D He MeV
21
22
30
1
21
21
31
1
31
22
40
1
"
"
"
+ +
+ +
+ +
1
1
1
]]
]
gg
g
While the x rays and charged particles are easily shielded by the Target Chamber, the neutrons with energies up to 14 MeV are penetrating enough to escape the Target Chamber.
Since the neutrons are emitted promptly when the fusion reaction occurs, they are a hazard only at the time of a target shot. However, because of the high numbers of neutrons produced, they are the most significant radiation hazard associated with the operation of the OMEGA Laser System. The fluence per unit dose equivalent for monoenergetic neutrons is as follows:
Neutron Energy (MeV)
Fluence per unit dose equivalent
(neutrons/cm2/rem)
1.0 2.7 # 107
2.5 2.9 # 107
5.0 2.3 # 107
7.0 2.4 # 107
10.0 2.4 # 107
14.0 1.7 # 107
Considering that the Target Chamber OD is 129.92 inches (330 cm), a target shot that produces the maximum credible yield of 3 # 1015 neutrons would result in a dose of 516 rem at the surface of the Target Chamber (the lethal dose for 100% of the population is considered to be 900 rem).
Neutrons emanate from the target radially; thus, the neutron flux decreases due to spherical spreading (as a function of r–2 from Target Chamber Center). The concrete shielding around the Target Bay protects personnel external to the Target Bay from neutron radiation. Because of the beam holes in the shield wall, the shield does not protect personnel in the Laser Bay. Rather, excluding access to the Laser Bay during shots offers the necessary protection for personnel within LLE, and distance from the radiation source protects anyone external to the west end of the Laser Bay. Protection of personnel adjacent to the Laser Bay, i.e., in the Amplifier Test and Assembly areas, is offered by a combination of distance and the oblique angle in the straight line path from the target center to these areas. For a more detailed discussion of shielding see Section 2000.
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Neutrons interact with matter by either scattering or absorption. In scattering, the neutron’s kinetic energy is reduced by either elastic or inelastic collisions. The most effective energy transfer is by elastic collisions (as with a billiard ball that imparts all of its energy to another billiard ball when it hits it head on). Thus, the best shielding is low-Z materials, in particular hydrogenous material since the mass of a hydrogen nucleus equals that of a neutron. The effectiveness of the concrete shield is primarily due to the included hydrated water. In inelastic scattering, only part of a neutron’s kinetic energy is transferred to another atom, and the neutron scatters in another direction with slightly less energy (as when a billiard ball hits a bowling ball a glancing blow). In absorption, a neutron is absorbed by an atom’s nucleus. The nucleus in turn becomes excited and releases its excess energy by either the prompt or delayed emission of gamma, beta, proton, or other radiation.
1002 OMEGA EP RadiationThe interaction of the high-intensity OMEGA EP laser beams with planar high-Z targets produces fast electrons e– that, in turn, produce hard x rays via bremsstrahlung (braking radiation). While the spreading of the lower-energy x rays, kT = 0.1 MeV, is uniformly spherical over a solid angle of 4r, the spreading of higher-energy x rays is directional. X rays of energy 1 MeV and 10 MeV are in approximately 90° and 45° cones, respectively, along the axis of the incoming laser beam (Fig. I-1). OMEGA EP was designed to direct the short-pulse backlighter beams north and the sidelighting beam west to minimize the amount of shielding required. Very energetic protons
Fig. I-1The laser accelerates the electrons, and the charge separation sets the ions in motion.
G6507
Ions, debris
Target
g, e–, p
g, e–
e–, p
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are also produced as a result of the interaction. Protons are produced from residual water on or in the target as the electrons are stripped away. As the electrons leave the target, the protons follow normal to the target. The protons are effectively stopped by the Target Chamber.
Neutrons are produced from a D-D fusion reaction (Section 1001) if deuterium targets are employed. These neutrons have an energy of 2.45 MeV and spread spherically. An additional source of high-energy neutrons is a (cn) reaction; however, this source is two to three orders of magnitude less than the neutrons from the D-D reaction.
The cn reaction also produces radioactive activation products within the target chamber that decay with varying half-lives and are a source of c radation. This source must be considered when entering the OMEGA EP target chamber.
Gamma radiation is produced from the decay of neutron activation products (Section 1003). This source is significantly less than that on OMEGA due to the lower neutron flux on OMEGA EP.
From a radiation control perspective, the neutron radiation dominates the general area shielding and the hard x rays dominate the directional shielding. Radiation protection is provided by a combination of shielding and the use of closed access to the OMEGA and OMEGA EP facilities depending on the type of experiment. For a more detailed discussion of the OMEGAEP shielding see Section 2001.
1003 Neutron Activation Gamma RadiationThe neutron radiation produced from fusion over time can activate the structural material in the Target Bay. The activated isotopes in turn decay and emit gamma radiation. The primary contribution to the activation radiation comes from the activation of the aluminum alloy (Al) Target Chamber. The decay of two nuclides formed by this activation dominates the radiation from the chamber. Na-24 (half-life = 15 h) emits most of the radiation shortly after a target shot, whereas Mn-54 (half-life = 313 days) contributes most of the long-term radiation. Of a secondary concern is activation of the iron in the Target Bay structures. The nuclide Fe-59 (half-life = 45 days) would be the primary activation product in the unlikely event that structure activation is observed.
The primary activation and decay reactions are as follows:
*
* . . .
. . .
n
n
1 4 1 37 2 75
0 83 0 84
Na Na Mg MeV MeV MeV
Mn Mn Fe MeV MeV
111
2311
2412
24
125
5325
5426
54
" "
" "
b c c
b c
+ + + +
+ + +
] ] ]
] ]
g g g
g g
Figures I-2 and I-3 show the specific activation levels of the OMEGA Target Chamber by a 3 # 1015 neutron-yield shot after ten years with 12 shots per year at this level. With these activation levels the radiation level will be reduced to <1 mrem/h at the surface of the Target Chamber or <0.01 mrem/h at a distance of 5 m from the Target Chamber in less than two days after such a shot occurs. The integrated neutron yield over time will be used in conjunction with periodic
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radiation surveys to determine if neutron activation will require personnel monitoring and stay times to restrict personnel exposure.
Since gamma rays are not charged particles, interactions with matter are not a result of electrostatic forces as with alpha and beta interactions. Rather, gamma or x rays transfer energy by direct interaction with atoms. There are three types of interactions:
Photoelectric effect – The photon transfers all of its energy to an orbital electron, causing its ejection. This effect is most probable for low-energy photons and high-Z materials.
Compton scattering – The photon transfers part of its energy in ejecting an electron. The remainder of the energy is emitted as a secondary photon, which might scatter in any direction.
Pair production – The photon (with a minimum energy of 1.02 MeV) interacts with the nucleus of an atom to produce an electron (b–) and a positron (b+) pair and a photon of lower energy.
1004 Tritium Beta Radiation Tritium is used as a fusion fuel in ICF target experiments. As an isotope of hydrogen it behaves chemically and physically like hydrogen. In either the gaseous (HT) or vapor (HTO) form, continuous isotopic exchange with the H in materials, plants, and animals occurs. Additionally, because of the small size of the hydrogen molecule, it easily penetrates the grain boundaries and interstices of materials. It is these properties of tritium that make its use and handling more difficult than other radioactive materials; e.g., tritium in either the HT or HTO form can enter the body through either the mouth, nose, or skin, and, because it is a gas and not a particulate, it cannot be filtered. Additionally, because tritium is absorbed in materials, it out-gases as an inverse function of the vapor pressure and undergoes isotopic exchange as a direct function of vapor pressure. Thus, because of out-gassing over time, a material that has been exposed to tritium is very difficult to certify as being decontaminated. See Section 3007 for a discussion
Fig. I-2Maximum design target chamber specific activity.
Fig. I-3Maximum design target chamber specific activity.
G6508
10–5
10–6
10–7
10–8
10–9
10–9
10–10
10–8
0 8Time (h) Time (days)
Ci/c
c
16 24 3020100
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of decontamination. Figure I-4 shows the outgassing rate of tritium from a surface as a function of the surface activity level.
Tritium decays with a half-life of 12.3 years as follows:
. , . .T 18 6 5 7He keV maximum keV average32
3" b+ -1 _ i
Up to 15,000 Ci of tritium is stored in the uranium getters of the Tritium Fill Station (TFS). The tritium is used to fill warm CH capsules in the TFS or cryogenic capsules in the CTHS (Cryogenic Target Handling System). (See “Volume IV–CTHS Description” for more information on the TFS and CTHS.) These targets are transported and inserted into the Target Chamber in a manner that ensures against release to the environment. After a tritium target is imploded, the residual tritium is absorbed into the Target Chamber and diagnostics and is subsequently removed via the Target Chamber vacuum systems. Most of the residual tritium is collected in the cryogenic vacuum pumps connected to the Target Chamber. When these pumps are regenerated, the tritium is collected in a scavenger bed composed of a zirconium-iron getter. Tritium is also released from the Target Chamber and diagnostics when they are evacuated by the main Target Chamber roughing pumps and the diagnostic roughing and turbo-backing vacuum pumps, respectively. These streams are processed by a tritium removal system prior to being discharged. Separate
Fig. I-4Tritium outgassing rate as a function of surface activity.
G7137J1
Note: outgassing at room temperature
1 monolayer/h (each particle labelled with a T atom)
105 106 107 108 109
100
10–1
10–2
101
102
103
104
1010 1011 1012
Surface activity (DPM/100 cm2)
Outgas rate (nCi/h/100 cm2) = 7 # 10–6 Surface activity0.74 (DPM/100 cm2)
Out
gass
ing
rate
(nC
i/h/1
00 c
m2 )
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ventilation exhaust stacks from the TFS and CTHS room (Room 157) and the target vacuum systems are monitored to measure the integral amount of tritium released to the environment.
As a charged particle, beta radiation causes ionizations as well as interactions as it passes through matter. Due to its smaller mass and lower charge, it is not as densely ionizing as an alpha particle, thus it may travel slightly farther through matter (e.g., an energetic beta can travel a few meters through air, but a tritium beta can travel only a few millimeters through air). The negatively charged beta particle can also interact with the positively charged nucleus causing the release of x rays as the beta deflects (bremsstrahlung radiation). The probability of bremsstrahlung radiation is proportional to an atom’s Z number. Therefore, effective shielding that minimizes bremsstrahlung radiation includes low-Z materials, such as plastic, wood, aluminum, etc. Low-energy beta radiation is easily shielded by a piece of paper; therefore it is only an internal radiation hazard. In the case of tritium, the beta particle is of such low energy it cannot be detected on film badges or thermoluminescent dosimeters (TLD’s) used to monitor personnel exposure. Accordingly, film badges or TLD’s are not required when working with or around tritium. Rather, urinalysis testing of personnel who work with >100 mCi of tritium is required within one week of exposure; or, for continuous exposure, weekly testing is required.
1005 Surface ContaminationSurface contamination is loose radioactive material that can be removed from surfaces and may therefore be easily spread. Surface contamination is normally only an internal radiological hazard. Thus, personnel protection can be provided by ensuring that such contamination does not enter the body. The method of protection depends upon whether or not the surface contamination is filterable. Tritium in the form of free HT or HTO is not filterable. Thus, protection from tritium surface contamination is afforded by wearing rubber or plastic covering over parts of the body that are likely to contact tritiated components (normally, rubber gloves when handling tritiated components and full anticontaminiation clothing, including rubber gloves, filter masks, and shoe coverings, when entering the Target Chamber). Where the tritium is contained in target debris, such as inside the Target Chamber, it is filterable. The only other possible source of surface contamination at LLE is from the ablation of activated Target Chamber or diagnostic material. This is not expected to be a concern at LLE; however, any precautions to protect personnel from tritium will likewise protect them from this source of particulate material. Surface contamination is detected by taking wipe survey samples as described in Section 3004.
1006 Airborne RadiationAirborne radiation may be in the form of gaseous or particulate radioactive material. There are two possible sources of airborne radiation at LLE: tritium and neutron activation of air. Tritium comes from the TFS and tritium targets while neutron activation of air is given by the following reactions:
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*
*
*
. . .
. . .
. . .
max
sec max
sec max
n
n
n p
1 8 2 49 1
7 1 10 4 6 13
7 1 10 4 6 13
3 29
3
3
Ar Ar hr K MeV MeV
N N O MeV MeV
O N O MeV MeV
>
>
>
01
1840
1841
1941
01
715
716
816
01
816
716
11
816
"
"
"
b c
b c
b c
+ + +
+ + +
+ + + +
^ ^
] ^
] ^
h h
g h
g h
For a maximum credible yield DT shot of 3 # 1015 neutrons, the maximum instantaneous airborne activity as a function of distance from the center of the Target Chamber is given as follows:
Distance(cm)
Activity
(nCi/m3)
540 2.9
990 1.0
1020 0.97
Since both Ar41 and N16 are airborne gases that give off gamma radiation, they are primarily external radiation hazards. The applicable limit for submersion in a hemispherical semi-infinite cloud of Ar41 is 3 nCi/m3. Since the average activity in a “finite”-size target bay is less than this limit and recognizing the short radiological half-life and the even shorter effective half-life considering ventilation, any exposure from Ar41 is insignificant. The half-life of N16 is so short that it is effectively gone within a minute after a shot and is therefore not a radiological hazard.
All normal tritium-handling operations are conducted in a manner to ensure that atmospheric levels are below the applicable airborne limits. To ensure compliance with environmental limits, the two exhaust stacks that could possibly contain tritium are monitored by Environmental Protection Agency (EPA) compliance monitors.
1007 Biological Effects of RadiationRadiation can effect living tissue by mutating, killing, or otherwise damaging cells. There is no substantiated threshold for genetic effects; however, it is known that the magnitude of these effects increases with exposure. The radio sensitivity of cells is directly proportional to their reproductive rate and inversely proportional to their degree of differentiation. Thus, blood-forming organs, digestive organs, reproductive organs, and embryos are more highly radiosensitive than nerve cells, muscle tissue, and the vascular system. The following are the effects of acute radiation doses:
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Dose (rads) Effect<5 No detectable clinical effects
5–25 Some changes noted in chromosomes, no physical effects75–125 Vomiting in 10% of exposed population
450 Lethal dose for 50% of the exposed population after 30 days300–900 Hematopoetic Syndrome: death in 10 to 15 days after exposure. Changes in
lymphocytes causes increased susceptibility to infection.900–10,000 Gastrointestinal Syndrome: most die in 3 to 5 days after exposure. The
gastrointestinal tract loses its absorptive functions. Symptoms are nausea, vomiting, salivation, dehydration, and weight loss.
>10,000 Central Nervous System Syndrome: death occurs in 1 to 2 days after exposure. Symptoms are hyperexcitability and incoordination in minutes followed by cardiovascular collapse.
>100,000 Molecular Death: death occurs almost immediately due to inactivation of basic metabolic processes.
1008 Radiation Protection PrinciplesThe aim of radiation protection is to reduce all radiation exposures to as low as reasonably achievable (ALARA). This is done by applying time, distance, and/or shielding.
Time – Minimize the exposure time to radiation sources to reduce the dose equivalent since Dose Equivalent = Dose Rate # Time. Since OMEGA is a pulsed source, the number of shots is equivalent to time.
Distance – Maximize the distance between a radiation source and the exposed person. This causes the dose rate to decrease by spreading. For point sources, spherical spreading applies and the dose rate decreases by a factor of 1/r2:
r rD D1 2 2 12
= ` j
For OMEGA, closed access ensures that personnel are at a safe distance.
Shielding – Decrease the radiation dose rate by inserting an attenuating/absorbing material between the radiation source and the exposed person. The effectiveness of a shielding material depends upon the type and energy of the radiation. For example:
Alpha particles – easily shielded by a piece of paper or a few centimeters of air; thus they present no external radiation hazard.
Beta particles – easily shielded by 1/4 in. or less of a low-Z material such as aluminum, plastic (Lucite or Plexiglass), or wood. Small thicknesses of a high-Z material should be avoided since more-penetrating bremsstrahlung radiation (x rays) will be produced.
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Neutrons and gamma and x rays – Since these types of radiation are more penetrating, their shielding is usually handled more rigorously.
R = R0e–nx
where R = radiation rate n = linear absorption coefficient (a function of material and type and energy of radiation) x = shielding material thickness
Often, the coefficient is not used directly; rather, the half-thickness (L1/2) of the material is used, where n = ln 2/L1/2. To shield for gamma or x rays, a high-Z material such as lead is most effective, whereas for neutrons, a low-Z hydrogenous material such as water, oil, or cement is most effective. Some typical shielding half-thicknesses are as follows:
Type Radiation Energy/Nuclide Half-thickness
gamma or x ray 1.27 MeV/Na24 1.0 cm of Pb
gamma or x ray 0.66 MeV/Cs137 0.54 cm of Pb
gamma or x ray 0.36 MeV/I131 0.18 cm of Pb
neutrons 10 MeV 7.64 cm of H2O
1009 Summary of Radiological LimitsA summary of the environmental and personnel protection radiological limits of concern to LLE is presented in this section. This summary is based on the environmental limits contained in NYS Department of Environmental Conservation publication 6 NYCRR Part 380 (Rules and Regulations for Prevention and Control of Environmental Pollution by Radioactive Materials) and US EPA compliance standards contained in the Code of Federal Regulations, 40 CFR part 61, subpart I, and the personnel protection limits contained in the NYS Department of Health Sanitary Code, Title 10, Chapter I, part 16 (Ionizing Radiation) that are implemented at the University of Rochester in the UR Radiation Safety Manual. For a detailed listing and explanation of these limits, these references should be consulted.
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Tritium Limits
Surface contamination(based on controlling radioactive material)
1000 dpm/100 cm2
Airborne limit in radiological work areas for HTO (applicable to personnel qualified as Radiation Worker, based on exposure for 2000 hr/yr and a total dose equivalent of 5 rem/yr)
20 nCi/m3
Airborne limit for general population for HTO(applicable to general population based on continuous exposure and a total dose equivalant of 50 mrem/yr to allow exposure to all age groups)
0.1 nCi/m3
NYS DEC non-permit stack limit(10% of airborne limit for general population)
0.01 nCi/m3
Drinking water limit(based on a total dose equivalant of 50 mrem/yr)
1 # 10–3 nCi/ml
Water sewage disposal limit 22,000 dpm/ml
Annual limit on intake (ALI) (exposure of 5 rem)
80 mCi
General External Radiation Limits
Occupational Radiation Worker Annual LimitsTotal effective dose equivalant to whole bodyTotal effective dose equivalant to embryo/fetusTotal effective dose equivalant to minors (<18 yr)
orSum of deep dose equivalent and committeddose equivalent to any individual organ or tissueother than the lens of the eye1
5 rem/yr500 mrem500 mr/yr
50 rem/yr
Eye dose equivalent1
Shallow dose equivalent to skin1
Extremity dose equivalent1
15 rem/yr50 rem/yr50 rem/yr
Non Radiation Worker Annual LimitTotal effective dose equivalent 100 mrem/yr
Radiation Area(film badge monitoring and control required)
>5 mrem/h at 30 cm from source
High Radiation Area(no entry allowed)
>100 mrem/h at 30 cm from source
Very High Radiation Area >500 rem/h at 1 m from source
1Limits to minors (<18 years old) are 10% of these limits.
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2000 OMEGA Shielding SystemA combination of shielding, distance, and shot cycles/yields is employed to limit radiation exposures in all accessible areas to <25% of the general population radiation exposure limit of 100 mrem/yr. The neutron shielding is conservatively designed to limit exposures on the basis of ten maximum credible yield shots of 3 # 1015 (14.1-MeV) neutrons per year. This maximum credible yield is used to provide conservative dose calculations and shield design since it represents the absolute maximum conceivable yield. In actuality the average expected neutron yields are from 1010 to 1014 and the maximum credible yield of 3 # 1015 neutrons may be approached only with cryogenic DT targets.
The radiation shielding design is discussed in more detail in the Environmental Assessment for the OMEGA Upgrade Project. The radiation levels detailed in this section are based on three sources as modified by the actual shielding installed. Report Number 6, “Radiation and Health Safety” of December 16, 1975, by United Engineering and Constructors, Inc., documents the design criteria of the original OMEGA laser system. For the upgrade, computer simulations of the radiation levels were performed by the Corporate Research Center of the Grumman Corporation under contract (#US3411) with the U of R and by the Inertial Fusion Applications Group (Y division) at LLNL. The Grumman analysis identified the locations with the highest radiation levels, and the LLNL group performed specific calculations for these locations. Sky shine was not explicitly calculated but is estimated not to add more than 10% to the calculated radiation levels in accessible areas of concern.
The neutron shield shown in Fig. II-1(a) and described below consists of the concrete floor of the Target Bay and a light-weight concrete wall constructed around the perimeter of the TargetBay.
Floor: The concrete floor is 30 in. thick and is penetrated by a 7-ft-diam hole immediately below the Target Chamber and by several ventilation and service holes. This floor provides at least 30 in. of shielding in the path from the Target Chamber center to any area outside LaCave. Thus, all areas below the Target Bay and Laser Bay floors that are outside LaCave including the anteroom and darkroom of the north of LaCave are protected. Because of the penetrations in the Target Bay floor, access to LaCave except for the anteroom and the darkroom is precluded during any target shot that is expected to produce neutron yields >1010.
Part IIRadiation Protection Systems
2000 OMEGA Shielding System2001 OMEGA EP Shielding System2002 Tritium Fill Station 2003 Tritium Transport System2004 Target Area Tritium Removal System2005 Environmental Monitoring System2006 Radiation Detection Instruments
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Fig. II-1(b) South Wall: The south wall is 30 in. thick and extends to a height above the Target Chamber. It is penetrated by an emergency fire exit door on the east end. A 30-in. curtain shield constructed of large concrete blocks provides at least 30 in. of shielding between the Target Chamber center and any area of the door.
Fig. II-1(a)The neutron shield.
Curtainshield
Curtain shield
ESOControl Room
Targetchambercenter
G6509
G6510
Emergencyfire exit
Looking south
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Fig. II-1(c) East Wall: The east wall is 30 in. thick and extends to a height above the Target Chamber. The south portion is higher because it is part of the original building construction. The wall was extended during the upgrade building project completed in 1993 and is slightly lower to prevent placing additional unnecessary weight on the Target Bay foundation. This wall is penetrated by the large Target Bay door that was used during the construction period. After construction this door was filled in with blocks filled with concrete to provide 30 in. of shielding. A 4-ft # 4-ft hole was cut in the shield to provide a path for the OMEGA EP beams to OMEGA. Due to the shield penetration, closed access of the opposing facility is required under some circ*mstances (see Section 2001).
Fig. II-1(d) North Wall: The north wall is nominally 35.4 in. thick and extends to a height above the Target Chamber. To provide for the full shielding effectiveness for ten maximum credible yield shots, the addition of 1.82 in. of borated polyethylene may be required if yields and shot operations prove this to be necessary. This borated polyethylene was not added during upgrade building modifications in 1993 for cost considerations. If yields and the monitoring of shielding effectiveness dictate that this additional shielding is required, it will be added at a later date by attaching the borated polyethylene to the outside of the shield wall in the
G6511
Target Bay doorfilled in
Target Bay shield looking east
OMEGA EPbeam hole
G6512
Looking north
Normalaccess
LDLbeamhole
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areas considered necessary. Because of space restrictions in the area of the Cluster1 F-ASP and the stairwell leading to LaCave, the shielding thickness is staggered from 35.4in. on the east end to 33 in. on the west end such that 35.4 in. of shielding is maintained on a line from the Target Chamber center. This wall is penetrated by two openings: the normal entrance doorway and a beam hole that allows entrance of a beam from the Laser Development Laboratory. Each of these openings is provided with a curtain shield of concrete blocks to provide shielding between the Target Chamber center and any accessible external area.
Fig. II-1(e) West Wall: The west wall is 30 in. thick and extends nominally to a height above the Target Chamber. The wall is penetrated by 67 openings: sixty 18-in.-diam holes for the laser beams to pass from the Laser Bay to the Target Bay; six 3-in.-diam holes at the base of the wall for service lines, and the door opening to the Target Bay Viewing Gallery. Because the bottom of the door opening for the Viewing Gallery is above the Target Chamber center, protection is provided to all accessible areas outside the west end of the Laser Bay. The straight-line path from the Target Chamber center through the shielding in the vicinity of the 3-in. service openings is in excess of 30 in.; therefore protection is provided by the shielding. The impact of the sixty 18-in.-diam holes was the subject of a special study conducted by LLE and the Inertial Fusion Applications Group (Y division) at LLNL. Since the beam holes are to the north and south of the centerline of the west wall, protection to the west is provided by the shield wall. Protection is provided to the south of the Laser Bay by the fact that the Laser Bay floor is nominally 14 ft above ground level and accordingly access is restricted. Additionally, because of the angular path from the Target Chamber center through these holes, substantial (although less than 30 in.) shielding is provided. Thus, by a combination of shielding, distance, and accessibility, the area to the south meets the shielding design criteria. Since the Amplifier Test and Assembly areas are north of the
G6513
Targetchambercenter
Looking west
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Laser Bay and accessible during shot operations, these areas require special consideration. Figure II-1(f) details the geometry of the line-of-sight path of neutrons from the Target Chamber center to these areas and specifies the areas for which the radiation levels in Table II-1 were calculated. Since these areas do not meet the shielding design criteria as maximum credible neutron yields are approached, access to these areas may have to be restricted. The shielding effectiveness will be monitored in these areas as a function of neutron yields to determine if and when these areas must be included as “closed access” areas during shot operations.
The expected radiation levels for a maximum credible yield target shot of 3 # 1015 neutrons are detailed in Table II-1 for areas outside the perimeter of the shield. These levels may be extrapolated linearly for yields less than the maximum credible. These calculations take into consideration the shielding of the 4-in.-thick aluminum Target Chamber, the thickness of the concrete shield, and the distance from the Target Chamber center to the listed locations.
Fig. II-1(f)Laser Bay north zones.
G6514
Control Room
GowningRoom
Zone11
Zone10
Zone9
Zone8
Zone7
Zone6
Laser Bay Target Bay
Zone5
Zone4
Zone3
Zone2
Zone1
N
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Table II-1: Calculated Radiation Levels
Location Neutron Dose/ Shot of 3 # 1015
Neutrons
Gamma Dose/ Shot of 3 # 1015
Neutrons
Total Dose/ Shot of 3 # 1015
Neutrons
Total Dose/ Ten Shots of
3 # 1015 Neutrons
South of Target Bay 3 ft above ground level
1.54 mrem
0.17 mrem
1.71 mrem
17.1 mrem
East of Target Bay 3 ft above ground level
1.54 mrem
0.17 mrem
1.71 mrem
17.1 mrem
East of Target Bay at target level*
35.20 mrem
1.980 mrem
37.20 mrem
372.0 mrem
Control Room wall as built without borated polyethylene
10.00 mrem
0.30 mrem
10.30 mrem
103.0 mrem
Control Room at ESO station without borated polyethylene
6.80 mrem
0.20 mrem
7.00 mrem
70.0 mrem
Control Room wall with borated polyethylene (not existing)
2.50 mrem
0.30 mrem
2.80 mrem
28.0 mrem
Control Room at ESO station with borated polyethylene (not existing)
1.75 mrem
0.20 mrem
1.95 mrem
19.5 mrem
Laser Bay east-west centerline at wall (no access allowed)
15.80 mrem
0.90 mrem
16.70 mrem
167.0 mrem
Laser Bay west wall 0.91 mrem 0.05 mrem 0.96 mrem 9.6 mrem
Laser Bay Zone 1 (Anteroom)
19.80 mrem
~1.00 mrem
20.80 mrem
208.0 mrem
Laser Bay Zone 2 (Control Conference Room)
28.70 mrem
~1.50 mrem
30.20 mrem
302.0 mrem
Laser Bay Zone 3 (Rod Amplifier Room)
37.90 mrem
~2.00 mrem
39.90 mrem
399.0 mrem
Laser Bay Zone 4 (Rod Amplifier Room)
25.30 mrem
~1.20 mrem
26.50 mrem
265.0 mrem
Laser Bay Zone 5 (SSA Cleaning Room)
34.00 mrem
~1.90 mrem
35.90 mrem
359.0 mrem
Laser Bay Zone 6 (SSA Assembly Room)
18.90 mrem
~0.90 mrem
19.80 mrem
198.0 mrem
*excluding the effect of the 12-in. OMEGA EP west shield wall.
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2001 OMEGA EP Shielding SystemLike the OMEGA radiation protection system, OMEGA EP uses a combination of shielding, distance, and shot types/numbers to limit radiation exposure in all accessible areas to <25% of the general population radiation exposure limit of 100 mrem/yr. The shielding design is based on 100 shots per year that produce either the maximum x-ray and/or maximum neutron yields indicated below:
• X-ray maximum source function – Spectrum I = I0 eho/kT with kT = 0.1 MeV, 1 MeV, 10 MeV – Energy/shot 1000 J of x rays – Solid angle 4r for kT = 0.1 MeV 90° cone for kT = 1 MeV 45° cone for kT = 10 MeV
• Neutron maximum source function – Spectrum E = 2.45 MeV – Number n < 1012 – Solid angle 4r
The shielding shown in Fig. II-2 and described below consists of a normal-density concrete floor and a shield wall that surrounds the entire OMEGA EP bay to a height of 6.6 ft above the target chamber. The shielding design is based on a study entitled “Radiation Safety and Effects Analysis for OMEGA EP” prepared by Advanced Energy Systems, Inc., for the University ofRochester.
Floor: The concrete floor is 30 in. thick and is penetrated by a 3-ft-diam hole immediately below the Target Chamber and by several ventilation and service holes. This floor provides at least 30 in. of shielding in the path from the Target Chamber Center to any area outside the experimental diagnostic bays located below the Target Chamber area. This ensures that all areas below the floor and outside the experimental diagnostic areas remain at <25% of the general population’s yearly limit. Because of the penetrations between the target area and the experimental diagnostic area, this diagnostic area must be in closed access during any target shot.
North Shield Wall: Neutrons and high-energy x rays (1 and 10 MeV) control the design of the north shield wall. This shield wall is made of normal-density concrete that is 39.4 in. thick except for a 4-in.-thick, 20-ft # 20-ft cutout centered on Target Chamber Center. This cutout covers the 45° cone north of the Target Chamber that is expected to contain the directional 10-MeV x rays. This cutout allows the addition of 4 in. of lead, which is required for the shield to meet the <25mrem/yr design criteria for 10-MeV x rays. The shield is 21 ft, 4 in. high, which is approximately 6.6 ft above Target Chamber Center.
With 4 in. of lead inserted in the cutout, the shield meets its design criteria for all sources of radiation except for 1-MeV x rays. Since this radiation subtends a 90° cone north of Target Chamber Center, additional lead shielding varying from 0 to 2.75 in. thick outside the cutout area to a distance 41 ft on either side of the shield-target chamber center line would have to be installed to meet the design criteria. The necessity for this shielding will be determined during the activation program and either the shielding will be installed or the number of high x-ray
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Fig. II-2OMEGA EP shield.
G6515aJ1
Dry wall
12-in. �lledconcrete blocks
Curtain shield(this plus 2 others to south, not shown)
Both the OMEGA and OMEGA EP shields have a 4-ft × 4-ftbeam tube opening.
Beam transporttube from OMEGA
4-in. indentation in shield to allow installation of 4-in.c lead (if necessary)
NOTES:
1. Shield material is normal- density concrete. Formed except where 12-in. �lled concrete blocks are shown.
2. Shield is 21 ft, 4 in. high
39.4 in.
31.5 in.
12-in. �lledconcrete blocks
19 in.
16 in.
12 in.
82 ft
56 ft
16 ft
16 ft
20 ft
265 ft
N
TC
20.3 ft
21 ft
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yield shots will be restricted to remain within the radiation design criteria of accessible areas remaining <25 mrem per year.
East Shield Wall: Neutrons control the design of the east shield wall. This shield wall is poured concrete for the first 108 ft from the north and has a tapered thickness from north to south: 31.5in. for 56 ft, then 19 in. for 16 ft, then 16 in. for 16 ft, and then 12 in. for 20 ft. Thereafter, the shield is formed by 12-in.-thick concrete blocks filled with concrete. Where doorways enter the bays, curtain shields offset the entrance doors to provide shielding in the line of sight from the target chamber. The shield is 21 ft, 4 in. high, which is approximately 6.6 ft above Target Chamber Center.
South Shield Wall: Neutrons control the design of the south shield. This shield is formed by 12-in.-thick concrete blocks filled with concrete. The shield is 21 ft, 4 in. high, which is approximately 6.6 ft above target chamber center.
West Shield Wall: Neutrons control the design of the west shield under normal circ*mstances. If one short-pulse beam to sidelight a target is used, the shield performance is limited by 1- and 10-MeV x rays. To accommodate this, either OMEGA would have to be in closed access or additional lead shielding would be required. The shield, constructed as part of OMEGA EP, is formed by 12-in.-thick concrete blocks filled with concrete. The shield, in combination with the 30-in. OMEGA shield, provides 42 in. of shielding between OMEGA and OMEGA EP and vice versa.
To allow the OMEGA EP beams to pass to the OMEGA target chamber, a 4-ft # 4-ft hole penetrates both the OMEGA east shield and the OMEGA EP west shield wall. Accordingly, for independent shots on OMEGA or OMEGA EP, closed access in designated areas in the opposite facility is required under the following circ*mstances:
For OMEGA shots: • Closed access on top of GCC, OMEGA EP target area structure (TAS) upper deck,
GCC interior, and EP target chamber if >3 # 1011 neutrons on OMEGA (implemented as OMEGA Type 7b shots)
• Closed access to the entire EP Laser Bay if >3 # 1014 neutrons on OMEGA (implented as OMEGA Type 7c shots)
For OMEGA EP shots: • OMEGA access not restricted for UV shots, OMEGA EP neutron yield shots up to 1 #
1012 and OMEGA EP short-pulse backlighter shots with energies up to 2.1 kJ on target • OMEGA target bay must be in closed access for an OMEGA EP shot to the OMEGA
target chamber • OMEGA target bay must be in closed access for OMEGA EP sidelighter shots
2002 Tritium Fill StationAs originally constructed the Tritium Fill Station (TFS) consisted of the receiving and inventory loop, pumping system, DT storage loop, capsule charging loop, piping and valving, glovebox, ancillary systems, glovebox purification system, electrical and instrumentation systems,
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glovebox atmosphere monitors, control system, and the supporting facility. In 1995 the TFS was modified as follows: addition of a glovebox annex to allow for the handling and coating of filled targets, modification of the process loop to allow for the addition of cryogenic filling capabilities, replacement of the contact tube to allow filling of mounted targets, and installation of a cryogenic cooler. The original system is fully described in the Tritium Filling Station Environmental Assessment and the original Tritium Filling Station Design Manual, and the 1995 modifications are included on the updated as-built drawings. In 1998 the facilities containing the TFS were expanded to accommodate the cryogenic target handling system (CTHS), which was installed in 1999. For further information on this system see the CTHS Volume IV System Description (S-AA-M-31), Chap. 5.
In 2003, the TFS was moved to a new addition to Room 157 and a new glovebox (connected to the previously added annex) was added for tritium experiments. Additional upgrades to the TFS included modification and simplification of the glovebox cleanup system; upgrading the programmable logical controller (PLC) used to control the process; the addition of a new graphical user interface employing a touch panel; the removal of the Overhoff tritium sampling system; and the addition of new moisture analyzers, a flowmeter, and a pressure sensor in the cleanup loop.
In 2004 new instrumentation and valves were added to the TFS process equipment. In addition, a new double-contained process line interconnecting the TFS with the DT High-Pressure System (DTHPS) was completed. This line will serve as the means to transfer tritium between the TFS and the DTHPS. In 2005 a new computer was added to the control system, enabling the operation via a new graphical user interface, which includes a dynamic process schematic.
Overview of Room-Temperature FillThe maximum permissible tritium inventory at LLE is 1.5 grams of tritium (15,000 Ci). This tritium is reversibly stored in one of two uranium beds. At room temperature, the U-beds absorb deuterium/tritium (by converting DT to uranium hydride), and the tritium is released when the U-bed is heated to 425°C. When the system is not in use, the entire tritium inventory is stored in the U-beds in the form of uranium hydride (each of the two beds has a 26,400-Ci capacity for a 50/50 D/T mixture). Under normal operation the TFS can complete one loading cycle every three days. To improve the efficiency of DT transfer, it is condensed in the condensation cell to minimize back pressure in the U-bed.
The DT is transferred from the U-bed to the condensing cell and then to the assay volume. The assay volume is a 7.4-liter volume that has two pressure gauges and temperature gauges that are used to assay the contents. A portion of the DT is then recondensed in the condensation cell. The DT that is not condensed is returned to the second U-bed (referred to as the cold bed).
The condensation cell temperature is then raised to evaporate the DT and pressurize the contact cell where the targets reside. After the fill has been completed, the balance of the DT is transferred to the cold U-bed. The residual DT left in the process line is removed by circulating the residual DT over the cold U-bed using the Normetex pump. The system is then evacuated into a single-pass, dedicated clean-up train (process loop getters) before being expelled into the glovebox cleaning getters. The actual tritium content of each polymer capsule will be variable dependent
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upon the experimental program. A reference value of 12.5 mCi is assumed for gaseous targets, and a reference value of 0.3 Ci is assumed for cryogenic targets.
Overview of Cryogenic, High-Pressure FillThe TFS supplies DT for the cryogenic, high-pressure fills. The DT is first transferred to the condensation cell by heating the U-bed and condensing the DT in the condensation cell (as discussed in the previous section). The pressure in the system peaks at 1 atm during condensation but reaches low pressure (50 torr) at the end of the condensation cycle because nearly all of the DT gas is condensed. This allows all of the DT to be driven off the hot U-bed in one heating.
The DT is then expanded to the assay volume, and an assay is taken. Subsequently, the DT is transferred to the DTHPS (by condensing in the DTHPS condensation tube). The DTHPS will return portions of the inventory during the high-pressure fill cycle. Each time DT is returned, the DT is assayed and then transferred to the cold U-bed. The residual DT is then circulated over the cold U-bed and the TFS is evacuated. The high-pressure fill cycle is described in more detail in the CTHS Volume IV System Description.
Under normal operating conditions, the TFS was designed to achieve practically zero leakage of tritium from system components located in the glovebox. The glovebox serves as a second barrier to prevent tritium leakage into the atmosphere. Any tritium that enters the glovebox will be collected in the glovebox purification system. Therefore, by design the contribution of the TFS to the chronic ambient tritium concentration is negligible. As a third barrier to people within the UR/LLE building, the room housing the TFS is kept at a negative pressure to ensure zero leakage to adjacent spaces.
Tritium levels are monitored continuously inside the glovebox by a tritium monitor integral to the TFS. If this monitor detects excessive tritium, the TFS is automatically shutdown and the tritium is returned to the uranium beds.
To ensure safety, accidents that could affect either the general environment and population or individual UR/LLE employees were analyzed. The analysis concluded that there was no accident that would put either the general population or environment at risk. An accident that releases the entire inventory of tritium to the TFS room and thence to the environment is the worst possible accident. The TFS Radiological Safety Assessment evaluates the probability of this accident to be very remote since it would require dual failures (i.e., failure of the TFS system resulting in release to the glovebox and the simultaneous failure of the glovebox). This accident’s analyses and the consequences of an acute release of 15,000 Ci of tritium to the TFS room and thence to the environment are detailed below.
To calculate the potential radiation dose, the following assumptions were made:• Instantaneous release of 15,000 Ci of elemental tritium to the TFS room while a UR/LLE
staff member was inside.*
*The 1-h assumption is based on a ventilation half-life of 11.5 min. Considering that it takes approximately five half-lives for complete elimination, it would take approximately 1 h to exhaust all of the tritium from the TFS room to the environment.
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• Following the failure, it would take less than 1 min for the tritium alarm to annunciate and and no more than 2 min for the UR/LLE staff member to evacuate the room.
• Negligible oxidation of tritium occurs within the glovebox or the TFS room.
Based on the above assumptions, the effective whole body dose equivalent resulting from a 2-min inhalation exposure to elemental tritium is less than 6 mrem to the UR/LLE staff member.
To calculate the potential dose to the general public, the following assumptions were made:
• Release of 15,000 Ci of elemental tritium to the environment via the TFS room exhaust over a period of 1 h.
• Adverse weather conditions: summer, no rain, stable conditions (Pasquill Stability Class F) with wind speed of 2 m/s, and a low capping inversion height.
• The individual exposed remains downwind on the plume centerline for a period of 7days.• Exposure is from elemental tritium.
Based on the above assumptions, the radiation doses from exposure to elemental tritium and conclusions are as follows:
• Maximum individual doses (200 m downwind)Average general population (adult): 12 nremAverage general population (child): 10 nrem
• Dose at 2 km falls below 2 nrem.• Collective dose is unlikely to exceed 1 man-rem.
To ensure that the TFS is operated safely, all operators must be qualified as Radiation Safety Workers and system operators in accordance with the LFORM. To protect against the inadvertent release of tritium to either the building or the environment, the facility must be locked when no one is in attendance, and all operations must be performed strictly in accordance with the CTHS Volume V operating procedures.
2003 Tritium Transport Transport of Warm Tritum Targets: The tritium targets are transported in dedicated transport bottles from the Tritium Fill Station to the Target Positioner (TP) following procedure SS-5-4, Part 4 (OMEGA System Operations Manual, Vol. II). After a target is placed in the transport bottle from within the TFS glovebox, the bottle is swiped (and decontaminated if necessary), and then transported to the TP. When the bottle is uncapped at the TP, it is held at arms length and an Overhoff portable tritium monitor is used to detect tritium. Additional exhaust ventilation at the TP and the handling procedures outlined in procedure SS-5-4, Part 4 (OMEGA System Operations Manual, Vol. II) ensure that exposure to the operator is as low as reasonably achievable. Weekly urinalysis testing confirms that exposures are insignificant. At all times during this operation, the target, target support, and target transfer containers are under the direct and continuous supervision of a Radiation Worker qualified technician.
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Transport of Cryogenic Tritium Targets: Cryogenic tritium targets are transported in a Moving Cryostat Transport Cart in full containment. See CSO-9 for cryogenic target transfer from the FTS to an MCTC and SO-7 for transfer from the MCTC to the OMEGA Target Chamber.
2004 Target Area Tritium Removal SystemsTritium is introduced into the Target Chamber from the implosion of targets containing tritium. Since most of the unburned tritium will collect on the cryogenic vacuum pumps, the pumps are exhausted to a Tritium Scrubber System. A small fraction of the tritium will make its way to the Turbo Backing and Auxiliary Roughing vacuum pumps during normal operations and to the Main Roughing vacuum pumps during Target Chamber pump-down from atmospheric pressure. To support cryogenic DT operations, the removal of tritium from the Main Roughing, Turbo Backing, Auxiliary Roughing and Lower Pylon pump exhaust streams, and the MCTC Maintenance Room 150A is accomplished by a TC-TRS located in the Pump House Room 150B. The integral target chamber vacuum and tritium removal system is shown in Fig. II-3. The tritium removal system is composed of the following major components (exhaust monitoring systems are discussed in Section 2004). See the OMEGA System Description, Volume I, Chap. 12 for a detailed description of the TC-TRS.
Tritium Scrubber: The Tritium Scrubber System collects tritium in its various forms when the cryogenic pumps are regenerated. The Tritium Scrubber consists of a molecular sieve bed to collect water, an input ionization chamber, a pre-heater chamber, a nickel bed to crack hydrocarbons and chemically absorb oxygen, a zirconium–iron alloy bed to collect HT, and an output ionization chamber. These components are housed in an integral unit located in LaCave. Based on regenerating the cryogenic pumps on a monthly basis, the beds are sized to receive 12 regenerations and still effectively reduce the tritium levels to below environmental limits. Data from the ion chambers is recorded and analyzed to determine the capture efficiency and to determine when the beds will be regenerated or replaced. The exhaust from the tritrium scrubber is directed to the TC-TRS to ensure environmental exhaust limits are met during regeneration.
Target Chamber Tritium Recovery System (TC-TRS): The TC-TRS removes trace levels of tritium from air purge streams and vacuum system exhaust streams associated with the OMEGA TC and the Cart Maintenance Room (Room 150A). Figure II-3 illustrates how the TC-TRS connects to the existing OMEGA system. Figure II-4 shows a process flow diagram for the TC-TRS. The trace levels of tritium are first catalytically oxidized into tritiated water; then the water vapor is subsequently removed from the air stream by adsorption on molecular sieve beds. The gas streams are processed in a continuous fashion. For a detailed description of the TC-TRS see the CTHS System Description, Chap. 12. The system components are described below.
The TC-TRS is composed of two skids: the Reactor Skid and the Molecular Sieve Skid. The two main functions of the Reactor Skid are to control flow into the TC-TRS and to catalytically oxidize tritium. Figure II-4 shows a process flow diagram for the TC-TRS.
The TC-TRS draws gas from the OMEGA system through an intake manifold into a regenerative side-channel blower. The TC-TRS automatically compensates for different levels of flow into the manifold. This is achieved by a system employing a recycle valve that controls the gas pressure
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Fig. II-3Present system.
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Fig. II-4Target Chamber Tritium Recovery System.
Temp
Temp
G6517J1
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receiverNitrogen
Reactor
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FV-8500
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Chilled watersupply/return
Chilled watersupply/return
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scrubber, and cartmaintenance room
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Exhaust stack
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in the manifold. The blower continuously operates at a constant flow rate of 60 scfm. When there is no gas load on the system, 100% of the gas that leaves the blower is recycled back via the recycle valve. The recycle loop is comprised of the blower, the reactor, a regenerative heat exchanger, a preheater, an aftercooler, and a large tank—the Low-Pressure Receiver (LPR). The blower takes suction from the LPR as well as from the intake manifold. Gas can flow either back to the LPR or onto the Molecular Sieve Skid. When large loads of gas are pumped into the intake manifold, recycle is choked and all the gas that exits the blower is passed to the rest of the system. The pressure in the intake manifold is monitored and used to control the amount of recycle flow.
The reactor converts elemental tritium and trace tritiated organic compounds into HTO and CO2. The reactor employs 300 lb of a palladium-based catalyst (a “recombiner”) operating at 400°C. The reactor maintains this temperature very closely since there is a constant flow of gas through it, regardless of the flow into the intake manifold of the TC-TRS.
Once gas leaves the Reactor Skid, it flows to the Molecular Sieve Skid where molecular sieve beds (300 lb each) adsorb the HTO and water. Three beds are employed in such a manner that while one is operating as a scrubber, a second can be regenerated. The third bed is used to polish the effluent from the regeneration process. During regeneration, hot nitrogen gas flows through the bed to be regenerated, releasing water and saturating the exhaust stream. The regeneration process employs a watercooled condenser to remove approximately 85% of the water from the saturated stream. The system automatically measures the rate of recovery of condensate. The condensed water is sampled for tritium: if it is below the limit for disposal 10 pCi/L (1 # 10–2nCi/ml), it is disposed via the sewer; if >10–2 nCi/ml but <0.5 nCi/ml, it is disposed of as radiation waste, and if >0.5 nCi/ml, it is sent to a waste processor for recovery.
Room 157 Tritium Removal System (TRS): This TRS removes tritium from helium and air gas streams that originate from the OMEGA Cryogenic Target Handling System (CTHS). The TRS was designed and built to support the use of tritium in the CTHS. For a detailed description of the Room 157 TRS see the CTHS System Description, Chap. 12.
The main objectives of the TRS are as follows:
• Remove sufficient tritium from the exhaust streams of the CTHS vacuum pumps so that exhaust concentrations do not exceed 1mCi/m3 and that the total activity of tritium released is kept under 1 Ci per year.
• Remove sufficient tritium from the glovebox atmospheres of the CTHS equipment so that background levels are maintained at or below 1mCi/m3.
• Maintain low levels of tritium in the DTHPS secondary containment spaces.• Provide high leak integrity and safe operation to limit operator exposure to tritium.
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Table II-2 summarizes the CTHS gas streams that enter the TRS for processing. There are two general types of feed streams: glovebox atmospheres and vacuum exhaust from CTHS vacuum pumps.
Table II-2: Summary of gas streams entering the TRS.
Gas Stream Gas Source Gas-Generating Operation Cleaning TRS Subsystem
Vacuum Pump Exhaust
High DT • DTHPS• FTS
• Target filling • Target transfer to MCTC
Tritium Cleanup Subsystem
Low DT • MCTC • Transport of targets between equipment
Tritium Cleanup Subsystem
Air • FTS target passthrough
• FTS interspace• MCTC• Characterization
• Inserting/removing target racks• Connecting MCTC with FTS• Pumping down MCTC from air• Pumping down characterization
chamber from air
Air Vacuum Cleanup Subsystem
Clean helium • FTS base • FTS dome• FTS cooling module
• Continuous• Continuous• Continuous
Stack to Exhaust or Tritium Cleanup Subsystem
Glovebox Cleanup
DTHPS glovebox • DTHPS glovebox • Continuous scrubbing of glovebox atmosphere
Glovebox Cleanup Subsystem
FTS glovebox • FTS glovebox • Continuous scrubbing of glovebox atmosphere
Glovebox Cleanup Subsystem
TFS glovebox • TFS glovebox • Continuous scrubbing of glovebox atmosphere
Glovebox Cleanup Subsystem
Other
DTHPS secondary containment
• DTHPS • Continuous cleaning/monitoring of high-pressure equipment
DTHPS Secondary Containment Cleanup Subsystem
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Exhaust gases from vacuum pumps originate from the CTHS system. A vacuum pump system helps to maintain the CTHS at cryogenic conditions by maintaining necessary vacuum. The effluent from the vacuum pumps is sent to the TRS for removal of tritium (detritiation) and other species including water and tritiated organics. In addition, there are several gloveboxes that surround and contain the CTHS equipment. The gas in these glovebox atmospheres become tritiated as a result of the tritium operations occurring within. Therefore, the gas in these gloveboxes needs to be constantly detritiated via the TRS.
In general, the TRS will process two types of gas: air and helium. Helium is used as the inert gas in the CTHS gloveboxes. Helium is also used as a process gas during CTHS operations. Additionally, there are operations where CTHS equipment needs to be opened to air and then pumped down again to vacuum. The effluent from this evacuation must also be treated. Therefore, both air and helium need to be accommodated by the TRS, which significantly affects the methods used for tritium removal. As a result, different processing techniques are used depending on whether the carrier gas is air or helium.
Three specific types of vacuum exhaust streams originate from the CTHS:
• Normally clean helium (from equipment that is normally not exposed to tritium)• Air (from equipment pump-outs)• A combined stream of highly tritiated helium (“high D-T”) and moderately tritiated
helium (“low D-T”) from equipment used to process tritium targets.
Another gas stream that the TRS processes is the containment volumes located within the DTHPS glovebox. The DTHPS system handles pure DT under high pressure and as a result has an additional containment around key equipment to contain any breach that might occur without release to the glovebox. Helium is used as the inert gas in these containment volumes. Tritium leakage is expected from the equipment in these volumes. Accordingly, these spaces must be continuously monitored and processed by the TRS to minimize tritium migration into the glovebox atmosphere.
There are four distinct cleanup subsystems in the TRS:
• Air Vac Cleanup Subsystem (ACU)• Tritium Cleanup Subsystem (TCU)• Glovebox Cleanup Subsystem (GCU)• DTHPS Secondary Containment Cleanup Subsystem(SECCON)
The ACU cleans up air streams originating from the CTHS Air Vac Manifold. The TCU cleans gas originating from the CTHS High and Low Tritium Vac manifold. The GCU handles all glovebox gas cleanup. The SECCON is a separate, dedicated cleanup subsystem that is physically located outside of the TRS and inside the DTHPS glovebox.
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Figure II-5 is an overview of these various subsystems and the gas streams that they process.
2005 Environmental Monitoring SystemSmall amounts of tritium are exhausted to the environment via two separate exhaust stacks that rise above the Target Bay roof. One exhaust stack, located on the north side of the Target Bay, receives the exhaust from the Tritium Fill Station and the Room 157 Tritium Removal System at 2200 scfm. The other exhaust stack, located on the south side of the Target Bay, receives the exhaust from the Target Chamber vacuum systems and/or the Target Chamber Tritrium Removal System at 1500 scfm. Both stacks are continuously monitored to verify that the DEC discharge permit limit is not exceeded. Both stacks are sampled by an Overhoff Technology Corporation (OTC) EPA tritium-in-air sampler. Samples from this system are taken on a batch basis and read by a liquid scintillation counter.
Fig. II-5Graphical overview of the TRS.
G6518
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TRS enclosure
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Clean gas
Tritium
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HTO
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Tritium
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Overview of Room 157 TRSTRS Feed Streams
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Discard tosanitary drainor ship out as rad waste
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Overhoff Tritium Air Sampler: This sampler collects both elemental tritium and tritium oxide samples from the exhaust stack air stream to verify compliance with the NYS DEC discharge permit. A pump controlled by an adjustable constant flow controller draws a representative sample from the exhaust line and passes it through two sets of 50-ml vials containing liquid scintillation fluid separated by a high-efficiency (typically 99%) catalytic oxidizer. The oxide form of tritium is collected by the first two vials in the process stream, and elemental tritium is collected by the second two vials after it is converted to the oxide form by the catalytic oxidizer. Each vial has a >95% collection efficiency. The vials are located on the front panel of the sampler for ready detachment and measureing the fluid activity by liquid scintillation counting. The system is calibrated to determine the percentage of tritium collected by the vials to allow accurate measurements of tritium. Typically, a collection time of 8 h will yield detection thresholds to <1 nCi/m3 (10–9 nCi/ml). Increasing the collection time can result in even lower detection thresholds.
Overhoff Tritium Air Sampler (EPA Compliance Monitor)
G6519
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Femto-TECH Tritium Monitor U24-D: This system is composed of an ion chamber for detection and a U24-D Control Unit for system control and display functions. This system measures tritium activity directly using an 1800-cc, active-volume ion chamber capable of resolving tritium to 0.1 nCi/m3 with an accuracy of !5%. Flow is provided by a 1-scfm diaphragm pump with flow measured by a rotameter. The measurement system is compensated up to 200 nCi/m3 for uniform gamma backgrounds using an alignment on the front panel. The system has high and low alarms set at 10 and 20 nCi/m3 per cubic meter, respectively.
Femto-TECH Tritium Monitor U24-D
G6520
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2006 Radiation Detection InstrumentsOverhoff Model 700 BAcC Portable Tritium Monitor: This monitor is used to conduct routine surveys upon opening potentially contaminated systems to ensure that airborne levels remain below the limits applicable to radiation workers. The instrument is a small, high-sensitivity, handheld, battery-operated, gamma-compensated airborne survey meter that can detect tritium in its elemental or oxide form. It uses four identical ionization chambers, two for tritium measurement and two for gamma compensation. A sample is drawn through the ionization chambers by means of a small rotary vane pump. An analog meter is used for measurement display using switch-selectable ranges of 0 to 10, 100, 1000, or 10,000 nCi/m3. The instrument exhibits a basic sensitivity of 1 nCi/m3, which allows detection below the 20 nCi/m3 limit applicable to radiation workers. Power is supplied by two 9-V batteries. The onset of battery depletion is signaled by the illumination of an LED located next to the meter face. An alarm-level–setting potentiometer adjustable over the full scale is located on the front panel. A steady tone is emitted by an acoustic signaler if the alarm point is exceeded. An intermittent tone is heard if the sample air flow has been interrupted. A more detailed description of this instrument is contained in the Operating Instructions provided by the manufacturer.
Overhoff Model 700 BAcC Portable Tritium Monitor
G6521
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Scintrix Limited Model 209 L Portable Tritium-in-Air Monitor: This monintor is used as a backup to the Overhoff Portable Tritium Monitor and, if necessary, during an emergency condition. Because it is not as sensitive as the Overhoff meter, it should not normally be used for routine operations. The instrumentation is a small, handheld, battery-operated, gamma-compensated airborne survey meter that can detect tritium in its elemental or oxide form. It uses two identical ionization chambers, one for tritium measurement and one for gamma compensation. A sample is drawn through the ionization chambers by means of a small rotary vane pump. A digital LCD readout is used for measurement display over a range of 0 to 20,000 nCi/m3 with a resolution of 10 nCi/m3. Power is supplied by five C-cell batteries. The onset of battery depletion is signaled by a blinking decimal point on the display. An electrometer output is used to trigger an alarm. The alarm may be set at either 100, 500, or 1000 nCi/m3; it is set at the factory to alarm at 500nCi/m3. A more detailed description of this instrument is contained in the Technical Manual provided by the manufacturer.
G6522
Scintrex Limited Model 209 L Portable Tritium-in-Air Monitor
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Perkin Elmer Tri-Carb 2910TR Liquid Scintillation Counter: This instrument is used to assay tritium swipe and liquid samples. The 2910TR is a semiautomatic, self-calibrating, liquid scintillation counter that assays racks of 7-ml sample vials. The 2910TR includes a detector unit, lead shielding, counting electronics, keyboard and display, and output printer and is fitted with a 19 nCi Ba133 external source that is used to gather Compton scattering data from each sample for quench compensation.
Different samples types are identified automatically by barcode labels on the sample rack. Sample rack slot #1 will contain a background vial filled with 4 ml of a liquid scintillation co*cktail and a clean swipe from the package used for the survey. The sample rack final sample slot will contain a “co*cktail-only” background sample filled with only 4 ml of liquid scintillaion co*cktail. Quench correction, background subtraction, and specific calibration curves are employed along with digital spectrum analysis techniques to directly determine the DPM value for the sample.
A detailed description of this instrument is contained in the Instrument Manual provided by the manufacturer.
Perkin Elmer Tri-Carb 2910 TR Liquid Scintillation Counter
G9368J1
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Wallac Model 1409 Liquid Scintillation Counter: This instrument is used to assay tritium swipe and liquid samples. The 1409 is a semiautomatic, self-calibrating, liquid scintillation counter that assays racks of 20-ml sample vials. The 1409 includes a detector unit, lead shielding, counting electronics, keyboard and display, and output printer and is fitted with a 12 nCi Eu152 external source that is used to gather Compton scattering data from each sample for quench compensation.
Different samples types are identified automatically by barcode labels on the sample rack. Sample rack slot #1 will contain a background vial filled with 15 ml of a liquid scintillation co*cktail and a clean swipe from the package used for the survey. The sample rack final sample slot will contain a “co*cktail-only” background sample filled with only 15 ml of liquid scintillaion co*cktail. Quench correction, background subtraction, and specific calibration curves are employed along with digital spectrum analysis techniques to directly determine the DPM value for the sample.
Caution: Liquid activities that exceel 500,000 CPM will saturate the counter and must be diluted and recounted in order to obtain accurate results.
A detailed description of this instrument is contained in the Instrument Manual provided by the manufacturer.
Wallac Model 1409 Liquid Scintillation Counter
G6524
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Ludlum Model 3 Portable Survey Meter with a Model 44-9 Detector: This instrument is used to perform periodic and contact radiation surveys in the Target Bay and Target Chamber to measure the radiation levels caused by neutron activation of structural materials. The Model 3 is a portable GM radiation survey instrument with four linear ranges used in combination with dose rate (mR/h) or CPM meter dials. It is powered by two standard D-cell batteries that are tested when the selector switch is positioned to the battery test position. A speaker mounted on the instrument gives an audible indication of the relative dose rate being measured. A more detailed description of this instrument and its operation is contained in the Instruction Manual provided by the manufacturer.
Note: This model is calibrated for CPM.
Ludlum Model 3 Portable Survey Meter with a Model 44-9 Detector
G6525
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Ludlum Model 9 Ion Chamber: This instrument is used to perform area c surveys in the OMEGA Target Bay to measure the radiation levels caused by neutron activation of structural materials. The Ludlum Model 9 is a portable ion chamber instrument calibrated for exposure rates in the 0 to 5000 mrem/h range. Is is powered by two standard D-cell batteries. Warm-up time is 2 min until stabilized. Calibration change is less than 5% battery dependent when batteries are wihtin battery-check limits on the meter. Response time is 3 to 5 sec, depending on the range selected. A more detailed description of this instrument and its operation is contained in the instruction manual provided by the manufacturer.
Note: This model is calibrated for dose in mrem/h.
Ludlum Model 9 Ionization Chamber
Bottom viewof Model 9
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3000 Shielding Effectiveness Monitoring3001 Target Chamber Activation Surveys3002 Target Bay General Radiation Surveys3002 Airborne Radiation Surveys3003 Airborne Radiation Surveys3004 Surface Contamination Surveys3005 Liquid Activity Surveys3006 Anticontamination Clothing3007 Establishing Anticontamination Controlled Area3008 Target Chamber Entry3009 Decontamination Procedures3010 Internal Transfer of Tritium Targets3011 Radioactive Material Accountability and Disposal3012 LLE Monthly Tritium Inventory3013 Scintillation Counting3014 Personnel Monitoring3015 Material with Fixed Activity
3000 ShieldingeffectiveneSSMonitoringTo monitor that the OMEGA and OMEGA EP Target Bay shielding is performing to design specifications and to ensure that exposure limits applicable to the general population are not being exceeded, the radiation dose on the outside of the shield is monitored by using thermo-luminescent dosimeters (TLD) with CR39 obtained from the University’s Radiation Safety Unit. Specific monitored sites are detailed on Survey Map A-1 in Appendix A. These sites were selected to monitor the shield in general and the penetrations detailed in Sections 2000 and 2001, in particular, to ensure shielding effectiveness in limiting exposure to less than allowable limits.
The TLD’s with CR39 are exchanged for new ones quarterly or whenever the integrated neutron yield exceeds 1016 neutrons since the last exchange, whichever occurs earlier. The TLD’s are delivered to the Radiation Safety Unit for delivery to Global Dosimetry Solutions for processing. The dosimetry report is reviewed by the LLE Radiation Safety Officer to ascertain shielding effectiveness and cumulative doses in occupied spaces adjacent to the shielding. If required, access will be restricted to limiting areas, e.g., the Amplifier and Assembly Areas, during shots that produce high neutron yields. If required to limit general dose rates, the shot schedule will be modified to limit integrated neutron production over time. The dosimetry report together with any analysis or restrictions imposed is filed as a permanent record.
3001 targetchaMberactivationSurveySTo monitor for neutron activation of the OMEGA Target Chamber and the OMEGA EP Target Chamber, a contact gamma radiation measurement at specific control points is performed semi-annually. The control points to monitor are detailed in Survey Maps A-2a, A-2b, and A-2c for OMEGA and on Survey Maps A-3a, A-3b, A-3c, and A-3d for OMEGA EP in Appendix A.
Part IIIRequirements and Procedures
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These maps are also used to record and trend the data and are filed when completed. The survey is performed with the Ludlum Model 3 Portable Survey Meter with a Model 44-9 Detector by holding the probe in contact with the control point.
3002 targetbaygeneralradiationSurveySTarget Bay general area gamma radiation surveys are taken periodically to determine the trend of neutron activation of structural components, whether or not the Target Bay requires posting as a “Radiation Area,” and to determine entrance requirements and stay times should radiation levels exceed 5 mrem/h.
To determine the trend of neutron activation, a gamma radiation survey is conducted every six months or after the integral production of 1016 neutrons since the last survey, whichever is more frequent.
If general area radiation levels of $1 mrem/h are detected during a periodic survey, a gamma survey must be conducted concurrent with any Target Bay entry after a shot that produces $1015 neutrons. Additionally, any personnel entering the Target Bay prior to the completion of the survey must be monitored by a TLD.
Following any high-yield shot, the radiation level will be measured at 30 cm from any structure and 30 cm from the TC at location G5 indicated on Map A-2b. If the survey indicates $5 mrem/h, the “Radiation Area” lights are illuminated, and anyone entering the Target Bay must be monitored by a TLD. Under these circ*mstances, the LLE Radiation Safety Officer will be notified. Access will be controlled and stay times employed to limit personnel exposures to within limits.
The results of these gamma radiation surveys are logged on Survey Maps A-2a, A-2b, and A-2c for OMEGA and on Survey Maps A-3a, A-3b, A-3c, and A-3d for OMEGA EP in Appendix A for OMEGA EP and are filed when completed. For the points labeled “G,” a general area radiation reading is taken by holding the detector probe at waist level and turning 360°. The average reading obtained is recorded. For the points labeled “C,” a contact radiation reading is taken by holding the detector probe in contact with the designated point.
3003 airborneradiationSurveySTritium airborne radiation surveys are taken:
(1) when opening a component that has been exposed to tritium—e.g., the Target Chamber, diagnostics, and the Lower Pylon when removing the MCTC after a cryogenic DT shot, and vacuum pump systems that communicate with the Target Chamber,
(2) periodically while conducting decontamination procedures, and
(3) after an accidental release of tritium.
The Overhoff Model 700 BAcC Portable Tritium Monitor is used to verify that tritium is not being released above the limit applicable to radiation workers 20 nCi/m3 when initially opening diagnostic systems (e.g., the Target Positioner and 10-in. manipulators) during the conduct of DT cryogenic shot operations. If levels >20 nCi/m3 are detected, the diagnostic will be closed and purged to reduce the level of contaminiation.
Procedures for entering the Target Chamber are found in Section 3008 of this manual and in the LFORM Sec. 4005. The Overhoff Model 700 BAcC Portable Tritium Monitor is used to verify that the tritium concentration is below 20 nCi/m3 prior to entry.
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(Not applicable for OMEGA EP provided the surface contamination is below 1000 DPM/100 cm2 in the GCC.)
During general decontamination operations of material exceeding 100,000 dpm/100 cm2 conducted in LaCave or Room 136 (or other locations approved by the LLE Radiation Safety Officer), a tritium airborne survey must be conducted every 8 h using the Femto-TECH Tritium Monitor U24-D or equivalent to ensure that airborne levels are below 0.1 nCi/m3, the limit applicable to the general public. The results of these surveys will be recorded on Survey Log A-4 in Appendix A.
In the event of an accidental release of tritium or the spill of tritiated material or water, an airborne survey will be taken with the Overhoff Model 700 BAc C Portable Tritium Monitor to determine if areas must be evacuated and/or breathing apparatus donned. The results of these surveys will be recorded on Survey Log A-4 in Appendix A. (See Part IV for emergency procedures.)
3004 SurfacecontaMinationSurveySArea surface contamination surveys are conducted periodically in accessible areas adjacent to where tritium is handled, e.g., the Tritium Fill Station room, prior to allowing components that have been exposed to tritium to be removed from the Target Bay, TFS, TRS, or CTHS glovebox; prior to Target Chamber entry; during and after decontamination procedures; and after accidental spilling or release of tritium. Additionally, surface contamination surveys will be conducted during cryogenic DT operations, while performing maintenance on potentially contaminated equipment, on sinks used to discharge liquid waste via the sewer (see Section 3011), and prior to and during maintenance on drains used to discharge liquid waste. Survey results >1000 dpm/100 cm2 in accessible, uncontrolled areas are to be reported immediately to the LLE Radiation Safety Officer.
All accessible areas must be maintained at levels <1000 dpm/100 cm2; inaccessible “controlled surface contamination areas” should be maintained at levels <105 dpm/100 cm2. At LLE, the inside of the TFS, FTS, and DTHPS gloveboxes, the inside of diagnostics and ten-inch diagnostic manipulators (TIM’s), and decontamination areas, when established, are designated “controlled surface contamination areas.” TIM’s will be maintained <104 dpm/100 cm2 on surfaces that can be reached with the door open. Other TIM surfaces closer to the Target Chamber that cannot be reached will be maintained <50,000 dpm/cm2. The inside of the Target Chamber and CTHS components are highly contaminated and will not be maintained at any particular level.
Area surface contamination surveys are conducted by dragging a wipe over approximately 100 cm2 of the surface being surveyed and then counting the wipe in the Wallac Model 1409 or the Packard Tri-Carb Liquid Scintillation Counters. If the area is too small to swipe over 100 cm2, due to small component parts or irregular surfaces, as much of the area as possible will be wiped and the results will be recorded per wipe rather than per 100 cm2.
Area surface contamination surveys will be conducted at the following frequencies and recorded on Survey Map A-4 in Appendix A:
– OMEGA Target Chamber each entry, semi-annually– Room 157, LaCave, and Room 136 weekly– Pump House/TC-TRS Room 150B when condensate is transferred– Cart Maintenance Room 150A weekly, during DT MCTC maintenance– Controlled contamination area during decontamination/maintenance operations every 8 hours
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All materials removed from systems after being exposed to tritium, e.g., blast window assemblies, diagnostics, materials from the TFS glovebox, etc., must be controlled and handled as radioactive material until it is proven otherwise. To verify material to be uncontaminated, two consecutive surveys taken at least 8 h apart after completion of decontamination are required. Both consecutive survey results must be <1000 dpm/1002. One survey is not sufficient since tritium is known to diffuse to the surface over time. Only personnel who are trained as Radiation Workers will handle potentially contaminated materials, and controlled contamination procedures must be followed. When removing potentially contaminated material, personnel must wear rubber gloves, and the material must be immediately surveyed and placed in suitable containment such as a pet G container or plastic bag.
All survey results will be logged on one of the Survey Map A-4 series in Appendix A. If the survey results indicate contamination >1000 dpm/100 cm2, the item must be tagged and subsequently decontaminated as described in the paragraph above before it is released to uncontrolled areas. Whenever transferring potentially contaminated material outside of controlled surface contamination areas, it must be contained in suitable containment and transported by Radiation Worker–qualified personnel along a predetermined route. All contaminated material must be controlled by attaching a numbered tag indicating the type and level of contamination, and by logging the tag number, contamination levels, and location in a Radioactive Materials log. (See Section 3011 for the applicable Radioactive Material handling procedures.)
Prior to handling potentially contaminated material or entering controlled surface contamination areas, suitable anticontamination clothing must be worn (see Section 3006). Subsequent to removing anticontamination clothing, and if a risk of personal contamination exists (e.g., after contacting contamination levels >105 dpm/100 cm2), personnel shall smear their hands and any other portion of their body subject to contamination with a glycerol-wetted smear paper as described in the following paragraph. In the case of exiting the Target Chamber or a controlled surface contamination area, the hands and exposed skin on the face shall be wiped with a glycerol-wetted smear. For other areas, if only rubber gloves were worn and no potential exists for other parts of the body to have become contaminated, then only the hands must be smeared. The results of these personnel smearing surveys need not be recorded as long as all levels are <1000 dpm/100 cm2. If, however, any reading is >1000 dpm/100 cm2, then all readings must be recorded on Survey Map A-4a in Appendix A and a urine sample must be taken and sent to the UR Radiation Safety Unit for analysis.
A glycerol wipe is performed by squirting 0.25 ml of glycerine (glycerol) on a smear paper, rubbing two smear papers together to distribute the glycerine evenly on both, smearing the subject area, and counting the collected activity using the Liquid Scintillation Counter (LSC). After the smear is taken, the applicable body part will be washed with warm water and soap and rinsed with warm water.
3005 liquidactivitySurveySLiquid activity surveys are conducted periodically to monitor the activity levels of water used in ultrasonic sinks used for decontamination, waste from blast window decontamination, dedicated TRS chilled water systems, and condensate from molecular sieve drier regeneration. Highly contaminated samples from regeneration must be taken with a micro-pipette rather than 1 ml to prevent overranging the Wallac. Action will be taken to investigate and correct the cause of
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increasing levels of activity. The UR Radiation Safety Unit has authorized LLE to discharge liquid waste via the sewer as long as LLE has verified the activity as averaged over a month is <1 # 10−2 nCi/ml (see Section 3011).
Ultrasonic sinks used for decontamination are sampled after each use for decontamination and at least weekly. The samples are counted using the Liquid Scintillation Counter and logged on the Sample Activity Log A-3 in Appendix A. Additionally, a log will be maintained at the ultrasonic sink giving time, date, person using, RLM # of the item decontaminated, and the sample results. The LLE Radiation Safety Officer will be informed of any sample that reads >100,000 dpm/ml.
3006 anticontaMinationclothingAnticontamination clothing is worn to prevent contamination of personal clothing or skin. Full anticontamination clothing consists of full coveralls, hood, shoe covers, gloves, and a filtered mask or respirator. For particulate contamination, cloth clothing and a filtered mask are adequate; however, to protect against tritium, plastic clothing and an air-fed breathing apparatus may be required (see Section 1004). Partial contamination clothing consists of lab coat and gloves or lab coat, gloves, and shoe covers.
At LLE the following are the normal anticontamination clothing requirements:
Target Chamber entry <10,000 dpm/100 cm2 – rubber gloves, clean-room clothing with shoe covers, and
face mask>10,000 dpm/100 cm2 – double clean-room clothing with shoe covers, rubber gloves,
and face mask (double clothing is required to allow removal of one set when exiting the anticontamination area while still maintaining a set of clean-room clothing; additional hoods and shoe covers should be available at the control point to don when others are removed)
Decontamination area <1000 dpm/100 cm2 – lab coat, shoe covers, and rubber gloves>1000 dpm/100 cm2 – full clean-room clothing (coveralls) with shoe covers and
rubber glovesMaterial handling – rubber gloves when only the hands come into contact with
potentially contaminated materialSpecial procedures must be followed when exiting a controlled surface contamination area, e.g., the Target Chamber or a decontamination area. First, the shoe covers must be removed in a manner that allows one to step down on a “step-off” area adjacent to the controlled surface contamination area immediately after removing the shoe covers. Then the hood and coveralls are removed, followed by the gloves. When removing anticontamination clothing, it should be turned outside-in to avoid spreading any contamination. After removal, all anticontamination clothing must be placed in segregated radioactive material containers for disposal.
3007 eStabliShingacontrolledSurfacecontaMinationareaTo prevent the spread of contamination, a controlled surface contamination area shall be established whenever an area has or may have surface contamination in excess of established limits (>1000 dpm/100 cm2). A barrier must be established around the perimeter of controlled surface contamination areas to prevent inadvertent entry, and the barrier will be posted with yellow and magenta signs stating “Controlled Surface Contamination Area” “Do Not Enter.”
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Normally, entrance to and exit from a controlled surface contamination area shall be limited to one point, the “control point.”
The control point will have a step-off area made of a disposable material such as an absorbent mat on the floor immediately outside of the controlled surface contamination area. This step-off area shall be maintained contamination free by frequently surveying and changing as required. The control point shall also have two radioactive material collection bags/packages, one for material to be laundered and one for material to be processed for disposal. When full, the UR Radiation Safety Unit will be called to process material for disposal. A squirt bottle containing glycerol will be provided to allow personnel smearing in accordance with Section 3004 upon exiting from the area.
The control point established for Target Chamber entry shall be continuously manned whenever the Target Chamber is open and personnel are in the chamber. This “Control Point Watch” is responsible for ensuring both contamination control and for ensuring the safety of personnel.
The Blast Window Assembly (BWA) and LaCave experimental operations decontamination areas must be maintained <104 dpm/100 cm2 during decontamination work. At the end of the work period or the end of a shift, the area should be cleaned and surveyed to a level <1000 dpm/100 cm2. If contamination levels >10,000 dpm/cm2 are encountered, anticontamination clothing consisting of coveralls, gloves, and shoe covers must be worn and discarded or laundered after use in decontamination. The step-off area should ALWAYS be maintained below 1000 dpm/100 cm2. If the step-off area is surveyed >1000 dpm/100 cm2, follow the procedures of Section 4000 and notify the Group Leader and the OMAN OMEGA Operations supervisor immediately.
3008 targetchaMberentryTarget Chamber (TC) entry requires both the Shot Director’s and the Radiological Safety Officer’s approval. TC entry shall be performed in compliance with approved procedures that fulfill the requirements of Sections 3006, 3007, and 3008.
NoteWhen the Target Chamber access port is open, a Control Point Watch must be stationed at all times to control personnel entry, communicate to Control in the event of an Emergency, and effect radiological controls.
• The appropriate procedure checklist, Target Chamber Access Authorization form, and a Personnel and Material Entry Log MUST be at the Control Point and maintained current throughout the TC entry. All personnel, tools, and equipment MUST be logged in and out of the TC.
• A Controlled Surface Contamination Area in accordance with Section 3007 shall be established in the area adjacent to the access port prior to opening the port.
• The Control Point watchstander must be a qualified Radiation Worker.
• The Target Chamber shall be brought to atmospheric pressure and purged in accordance with OMEGA operating procedures.
• The Target Chamber airborne tritium levels must be <20 nCi/m3 in accordance with Section 3003. (Not applicable for OMEGA EP as long as tritium surface contamination is below 1000 dpm/100 cm2 in the GCC.)
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• A surface contamination survey shall be conducted in accordance with Section 3004. This shall include the access port and the adjacent area inside the Target Chamber (that area reachable from the access port without extending more than the head, trunk of the body, and arms inside the chamber). (Not applicable for OMEGA EP provided the surface contamination is below 1000 dpm/100 cm2 in the GCC.)
• For OMEGA EP target chamber only, a c survey using the Ludlum Model 9 ion chamber shall be conducted upon opening the access hatch. If radiation levels $5 mrem/h are detected, the LLE Radiation Safety Officer must be notified and control procedures required for a Radiation Area as outlined in Section 3002, paragraph 4 must be used.
• Only personnel who are qualified as Radiation Workers and have been fitted for respirators are allowed entry into the Target Chamber.
Target Chamber Close-Out• The Target Chamber Access Authorization Form will be used to close out the Target Chamber.
3009 decontaMinationProcedureSDue to its high mobility, tritium readily absorbs into the bulk of many materials as well as being present on the surface; subsequently it can outgas and readily spread. To release tritiated components from controlled contamination areas, surface contamination levels must be <1000 dpm/100 cm2. To control occupational exposure, the ICRP recommends that surface contamination levels in occupied areas, e.g., the Target Chamber when open for access, be maintained <2 # 107 dpm/100 cm2.
Tritium-decontamination techniques include washing, vacuuming, purging, thermal desorption, isotopic exchange, chemical or electrochemical etching, plasma discharge, and melting. Experience with the decontamination of the original OMEGA indicates that vacuuming and washing are sufficient for the contamination levels expected to be encountered. Should these methods fail to reduce contamination levels sufficiently, additional procedures will be implemented with the approval of the LLE Radiation Safety Officer. The following decontamination procedures will be used at LLE:
Decontamination must be performed within a controlled surface contamination area established in accordance with Section 3007.
Component surface contamination surveys in accordance with Section 3004 must be performed before, during, and subsequent to decontamination. Before a component can be considered decontaminated, it must have levels of <1000 dpm/100 cm2 on two consecutive surveys conducted at least 8 h apart.
Surveys of the controlled surface contamination area must be performed in accordance with Section 3004.
Appropriate anticontamination clothing in accordance with Section 3006 must be worn.
Where particulate material is present, such as target debris inside of the Target Chamber, vacuuming with an approved radiological vacuum cleaner shall be performed. The vacuum filter must be collected and transferred to the UR Radiation Safety Unit for disposal.
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Washing with soap (10% Brulin 8156D) and water. Paper wipes, Q-tips, etc., will be used as required to reach cracks and crevices. All materials used must be collected and transferred to the UR Radiation Safety Unit for disposal.
Ultrasonic cleaning using a solution of DC13 and water. The water in the ultrasonic sink will be sampled in accordance with Section 3005. Components will be dried by using either absorbent wipes or natural convection air drying. Residue from decontamination must be transferred to the UR Radiation Safety Unit.
For the Target Chamber, diagnostic inserters, the MCTC’s, etc., purging with the moist room air to the TC-TRS will be used to reduce the levels of contamination.
Surface contamination surveys will be logged on one of the Survey Map A-4 series in Appendix A. Before any component is released from a controlled area, it must have been shown to have <1000 dpm/100 cm2 surface contamination on two consecutive surveys conducted at least 8 h apart; this result must be logged on one of the Survey Map A-4 series.
Any component not successfully decontaminated to <1000 dpm/100 cm2 must be controlled as radioactive material using the procedures of Section 3011.
3010 internaltranSferoftritiuMtargetSTo prevent the uncontrolled release of tritium into the environment, tritium targets must be continuously contained and controlled during transfer from the Tritium Fill Station (TFS) to the Target Positioner. The Tritium Transport procedures described in Section 2002 and outlined in Procedure SS-5-4, Part 4 (OMEGA System Operations Manual, Vol. II) are designed to provide this continuous containment. To ensure proper operation, only Technicians qualified as both Experimental Systems Technicians and Radiation Workers will insert targets containing tritium into the Target Positioner. The transfer route to the Target Bay will be via the LaCave to Target Bay stairwell access. Targets shall be transferred to the Target Positioner in a dedicated target bottle and inserted manually, while monitoring with the Overhoff Model 700 BAc C Portable Tritium Monitor. Spent target support and container materials will be handled as contaminated material and will be under the same continuous control during the return to the TFS for disposal.
3011 radioactiveMaterialaccountabilityanddiSPoSalTo prevent the unauthorized or uncontrolled release of radioactive material, strict accountability procedures are required. For radioactive sources, the control and inventory procedures of the UR Radiation Safety Manual apply. For the control of generated radioactive material, this procedure supplements those of the UR Radiation Safety Manual. These procedures apply to all equipment and material that has the potential of being transported (since the Target Chamber, Tritium Fill Station, and CTHS are fixed pieces of equipment, they are exempted from the requirements of this section; however, component parts removed from these pieces of equipment must be handled in accordance with these procedures). At LLE, the most likely source of radioactive material is that generated through exposure to tritium. Secondary sources of radioactive material are structures activated by neutrons in OMEGA and components activated by high-energy cn reactions on OMEGA EP. Since the only source of transportable radioactive material at LLE is tritium, radioactive material requiring accountability under this section is that material that has surface contamination or suspected internal contamination of >1000 dpm/100 cm2.
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Equipment and components (other than fixed equipment, but including fixed equipment when it is removed) that are found to have surface contamination levels >1000 dpm/100 cm2 must be controlled as follows:
Attach a tag (shown below) that includes a control number, equipment or material description, isotope, level of activity, and date tagged.
Radioactive Material TagTag Number:Material Nomenclature:Surface Contamination:Date:
Log the radioactive material tag information into the Radioactive Material Control Log, A-5 in Appendix A; in addition include the current location of the tagged item, the ultimate disposition (decontaminated or transferred to UR Radiation Safety Unit), and the signature of the person verifying the ultimate disposition. There will be two such logs maintained, one by the Cryogenic and Tritium Facility Group and one by the Experimental Operations Group.
Radioactive material shall be stored in authorized locations only. These locations must be labeled and locked. Approved storage locations in LLE are as follows:
– Room 157 (under the TFS glovebox and under the fume hood)– An area located on the south side of the Target Bay– A decontamination area located in La Cave– A source locker located in Room 150B– The Blast Window Decontamination area, Room 136– Moving Cryostat Transfer Cart Maintenance Area, Room 150A
An inventory and audit of all radioactive material including reconciliation of the Radioactive Material Log shall be performed quarterly by the Cryogenic & Tritium Facility and Experimental Operations Group Leaders. The results of these audits must be reported in writing to the LLE Radiation Safety Officer.
Radioactive material that is no longer required will be transferred to the UR Radiation Safety Unit. Only the UR Radiation Safety Unit is authorized to dispose of radioactive material; under no circ*mstances will anyone from LLE dispose of radioactive material. The single exception to this is that LLE has been authorized (by RSO letter dated 13 August 1998) to discharge liquid wastes subject to compliance with the following paragraph:
“Tritiated liquid having an activity <1 # 10−2 nCi/ml (22,000 dpm/ml) may be disposed of via approved sewage drains. This includes liquid from ultrasonic sinks used for decontamination and liquid collected from blast window decontamination. The drains used to dispose of liquids must be marked as potentially contaminated to ensure proper radiological control precautions are taken prior to performing maintenance. For all liquids disposed of via the sewage drains, the sample activity and volume must be recorded and reported to the LLE Radiological Safety Officer with a copy to the UR Radiation Safety Officer. This report will include a copy of the scintillation counter printout annotated to identify samples which represent liquid discharges. Additionally, a cumulative record of the volume and activity of liquid will be maintained for
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each drain used to discharge liquid wastes. Subsequent to such liquid discharges, a surface contamination survey of sinks used for the discharge must be performed in accordance with Section 3004.”
3012 lleMonthlytritiuMinventoryRunning inventories shall be maintained for the tritium that exists within the Cryogenic Target Handling System (CTHS) and associated equipment and for tritium contained in warm targets. The Cryogenic and Tritium Facility Manager shall maintain the CTHS, associated equipment, and the warm target inventory. The CTHS inventory shall make an accounting of all the tritium within the CTHS and the following equipment: Tritium Fill Station (TFS) and the Tritium Removal Systems (OMEGA scrubber, TFS glovebox, Rm157 TRS, and TC-TRS). The inventory shall be kept using an electronic log in the format of Form A-2. The warm-target inventory shall be kept in the format of Form A-3. The inventories shall be submitted to the LLE Radiation Safety Officer monthly. For the CTHS inventory, if the amount of tritium contained in the system outside of the uranium beds exceeds 4% of the system total, the Cryogenic and Tritium Facility manager shall investigate the problem and notify the LLE RSO.
3013 ScintillationcountingScintillation counting is used to count contamination survey wipe samples and liquid samples such as water. A Wallac Model 1409 or Tri-Carb 2910TR Liquid Scintillation Counter is used for all scintillation counting performed at LLE. The procedures for operating the counter are contained in the applicable Instrument Manual.
Both units automatically determine quench, chemiluminescence, and counting efficiency and subtract background. A background sample must be prepared and placed in position in one of the correct (labeled) racks.
For water samples, the result in nCi/ml of counting a 1-ml sample is obtained by dividing the dpm of the sample by 2.22 # 106 dpm/nCi.
Caution: Liquid activities that exceel 500,000 CPM will saturate the counter and must be diluted and recounted in order to obtain accurate results.
3014 PerSonnelMonitoringAs long as the shield is verified by the procedures of Section 3000 to be performing to design criteria, TLD with CR 39 monitoring of personnel outside of the primary shielding is not required. Personnel TLD monitoring is required only in the x-ray laboratory, in the Target Bay should neutron activation increase the general area radiation levels there to >5 mrem/h, or when handling activated materials. Since tritium cannot be detected by a film badge or TLD, exposure to tritium is monitored by bioassay (urine analysis). Anyone using more than 100 mCi of tritium is required to have a bioassay performed within one week following a single operation and at weekly intervals for continuous operations. At LLE, the following personnel monitoring is required:
– X-ray laboratory personnel: Monitored by TLD counted quarterly via the UR Radiation Safety Unit.
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– Exp. Operations personnel: Monitored by TLD counted quarterly via the UR Radiation Safety Unit; weekly urine analysis by the UR Radiation Safety Unit anytime gaseous DT targets are handled or the Target Chamber is entered during a particular week.
– TFS operators: Weekly urine analysis by the UR Radiation Safety Unit when targets are filled, the TFS or CTHS gloveboxes are accessed, or maintenance is performed on highly contaminated CTHS components during a particular week.
– Radiation-area entrants: Anyone who enters the Target Bay when it is a radiation area is monitored by thermal luminescent dosimeter (TLD) 760 Badge counted monthly.
3015 MaterialwithfixedactivityGamma-radiation surveys will be taken whenever neutron or high-energy c-n activation of material is suspected. The level of fixed activation will be measured by bringing the Ludlum Model 9 portable ion chamber in contact with the activated material. Material with radiation levels exceeding 0.1 mrem/h will be designated as Radioactive Material. The activated material must be controlled by attaching a numbered tag indicating the level of activation, the date, and by logging the tag number, contamination level and location in the Radiation Materials log. Tagged material will be resurveyed in conjunction with the quarterly audit of the Radioactive Material Log. If the level of activity has decayed to <0.1 mrem/h, the material may be cleared from the log. Any work with this material must be carried out in designated radioactive areas by qualified radiation workers wearing film badges and a finger dosimeter.
Work on activated material with radiation levels exceeding 5 mrem/h on contact requires LLE Radiation Safety Officer approval.
Section 3011 describes the material accountability and disposal procedures.
3016 eStabliShingaradioactiveMaterialScontrolareaWork on activated material with radiation levels exceeding 5 mrem/h on contact requires LLE Radiation Safety Officer approval.
The work will be performed by a qualified radiation worker wearing a TLD and a finger dosimeter. A barrier must be established to prevent inadvertant entry at a distance that ensures the radiation levels do not exceed 0.1 mrem/h. The barrier will be posted with yellow and magenta signs stating “Radioactive Materials Control Area—Do Not Enter.” Entrance to and exit from the radioactive materials control area shall be limited to one point, the “control point.”
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4000 Spill of Radioactive Material4001 High Airborne Activity4002 Acute Release of Tritium (from Tritium Fill Station)4003 UR Security Acute Release of Tritium Emergency Procedure
Part IVEmergency Procedures
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4000 Spill of Radioactive Material
Note
Since the only potential spill at LLE is tritium, this procedure is tritium specific. It implements the procedural requirements found in Sec. 17 of the UR Radiation Safety Manual.
a. ImmediateActions
1. Stopthespillifthiscanbeaccomplishedwithoutriskofpersonalcontamination.Coverthespillwithabsorbentpaper.
2. Warnothers in theareaandnotifyyoursupervisor(thesupervisorshouldnotifytheLLERadiationSafetyOfficerwho,inturn,willnotifytheURRadiationSafetyUnit).
3. Isolatetheaffectedareasbyclosingdoors,puttingupbarriers,and/orguardingtheentrancestothearea.
4. Minimizeyourexposuretoradiationand/orradioactivematerials.
5. Securelocalfansifradioactivematerialcouldbespreadbythefans.
b. SupplementaryActions
1. CleanupthespillasdirectedbytheURRadiationSafetyUnit.
2. Completesurfacecontaminationsurveysbefore,during,andafterdecontaminationoftheaffectedarea.
3. Smearpersonnelwhomayhavebeencontaminated.
4. ObtainurinesamplesfrompersonnelwhomayhavebeenexposedaboveallowablelimitsandsubmitsamplestotheURRadiationSafetyUnitforanalysis.
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4001 High Airborne Activitya. Indications
1. Sustainedairborneactivity>20nCi/m3incontrolledareas.
2. Sustainedairborneactivity>5nCi/m3inuncontrolledareas.
3. TritiumMonitoralarm.
4. TritiumFillStationorCTHSgloveboxtritiumalarm.
b. ImmediateActions
1. Ifacutereleaseoftritiumissuspected,refertoSection 4002.
2. NotifytheLLERadiationSafetyOfficer.
3. Secureoperationsthatmayhavecausedthehighairborneactivity.
4. Rigtemporaryventilationundercontrolledconditionstoreduceairbornelevelsto<1nCi/m3totheTC-TRS.
5. ObtainanairbornereadingusingboththeOverhoffModel700BAcCPortableTritiumMonitorandthemore-sensitiveFemto-TECHTritiumMonitorU24-D.
6. Ifairbornelevelsare>5nCi/m3inuncontrolledareas,evacuatenon-RadiationWorkerpersonneltounaffectedareas.
7. Ifairbornelevelsare>20nCi/m3,limitstaytimestothefollowing:
Airborne Level nCi/m3
Stay Time
<20 Unlimited
20to100 40h
100to1000 4h
1000to10,000 1h
c. SupplementaryActions
1. ObtainurinesamplesfrompersonnelwhomayhavebeenexposedaboveallowablelimitsandsubmitsamplestotheURRadiationSafetyUnitforanalysis.
2. NotifytheURRadiationSafetyUnitatExt.5-3781.Submitanestimateofthetotalactivityreleased.
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4002 Acute Release of Tritiuma. Indications
1. TFSorCTHSgloveboxtritiumalarm
2. Room157tritiummonitoralarms(TMT-1001and/orTMT-1002)are>2000nCi/m3.Sustainedairborneactivity>5nCi/m3inuncontrollableareas.
b. ImmediateActions
1. EvacuateRoom157totheadjacentcorridor,ensuringthatboththeinnerroomandouterroomdoorsareshutandtheexhaustfanisrunning.
2. Passthewordonthegeneralannouncingsystem“Tritiumalarm,allnon-emergencypersonnelmovefromtheeffectedareatoadjacentareas.Remainindoors.Shutalldoorsandwindows.”
3. ContactFacilitySupport(JohnSawyerat585-729-2225)toshutthenorthsideoutsideairintakestothebuildingventilationsystem.
4. TheLLERadiationSafetyOfficeror,inhisabsence,theseniorqualifiedLLERadiationWorker from the Cryogenic &Tritium Facility will take charge of the emergencyresponseuntilURRadiationSafetyUnitpersonnelarrive.
5. EstablishacontrolpointinthecorridoroutsidetheslidingdoorsofRoom157.ThepersonnelwhoevacuatedRoom157shouldremaininthisareatopreventthespreadofpossiblecontamination.
6. LLERadiationSafetypersonnelwillconducttritiumairbornesurveysintheoccupiedareasoftheLLEcomplextoverifythattheatmosphereisenvironmentallysafeandthatthereleaseoftritiumhasbeenlimitedtoRoom157.
c. AdditionalImmediateActions
1. NotifyUniversityRadiationSafetyUnit(5-3781).
Securitypersonnelwillproceed toEastRiverRoadandMurlinDrive toclearanyofthepublicthatmaybesouthofEastRiverRoadandwithin200yardsoftheLLEcomplex.Thisshouldbeaccomplishedbypostingpatrolpersonnelatthefollowinglocations:300yardseastofMurlinDriveonEastRiverRoad,attheintersectionofEastRiverRoadandMurlinDrive,300yardssouthonMurlinDrivetowardWhipplePark,andattheentrancetoRiverRoadLaboratoryonEastRiverRoad.SecuritypersonnelshouldnotloiterinareastowardLLEfromtheseperimeterpointsuntilRadiationSafetypersonnelhavedeterminedthatitisenvironmentallysafetodoso.
University Radiation Safety Unit personnel will proceed to the scene to assumecommandoftheresponseactionsandtotakeperimeterairsamples.
d. SupplementaryActions
1. URRadiationSafetywillimmediatelynotifyandreporttoregulatoryauthoritiesasrequiredbyNYSDECPublicationof6NYCRR,Part380,Sec.380-9.
2. PerformpersonnelmonitoringanddecontaminationofpersonnelwhowereintheTFSroomatthetimeoftheemergencyoraresuspectedtohavebeenexposed.Perform
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testingfortritiuminurineofallpotentiallyexposedpersonnel.Thesesampleswillbesubmittednolaterthan6hoursaftertheincidentandnolaterthan24hoursfollowingtherelease.
3. PerformairborneandwipesurveysanddecontaminationofRoom157.Note:Personnelshalldonappropriateanticontaminationsuitspriortoentry,andstaytimesbasedonairbornelevelsshouldbeestablishedasfollows:
Airborne Level nCi/m3
Stay Time
<20 Unlimited
20to100 40h
100to1000 4h
1000to10,000 1h
4. SecuretheTFSandCTHSandascertainthedamageandcause.
5. DocumenttheincidentincludingallsurveyresultsandincorporatetheserecordsintotheTFSDecommissioningRecord.
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4003 UR Security Acute Release of Tritium Emergency Procedure (from LLE Tritium Fill Station)a. Duringon-dutyhoursorwhentheTFSisoperatingandoccupied
1. UniversitySecurityandURRadiationSafetywill take theactions specified in theattachedprocedure.
b. Duringoff-dutyhoursorwhentheTFSisnotoccupied
1. UniversitySecuritywill
(a) ImmediatelynotifyallofthefollowingLLEPersonnel(startingfromthetopoflist)
Office Cell
RogerJanezic 5-5728 585-465-9191
MichaelKoch 6-2677 585-472-4660
SalvatoreScarantino 5-7042 585-478-2070
PatrickRegan 3-1707 585-733-7851
WalterShmayda 5-5769 585-469-6340
SamuelMorse 5-9672 585-586-2068
(b) ImmediatelynotifytheDutyRadiationSafetyon-callpersonbycalling5-3781ordigitalpager14-1172.Ifnooneispresent,theprerecordedmessagewillgivethedutyperson’shomephoneandpagenumber.
(c) TaketheactionsspecifiedforSecurityinSection 4002.
2. LLEPersonnelcontactedwillimmediatelyreporttoLLE,attempttocontactotherLLEpersonnelonthecalllist,andtakeactionsspecifiedinSection 4002.
3. UniversityRadiationSafetypersonnelwillimmediatelyreporttoLLEandtakeactionsspecifiedintheattachedprocedure.IntheeventthatURRadiationSafetypersonnelare the first on the scene, they will take charge and take all actions specified inSection 4002untilrelievedbyqualifiedLLEpersonnel.
Page V-115 August 2011
LLE Radiological Controls ManualPart V: Maintenance Procedures
LLE RADCONMANLLEINST 6610F
5000 Tritium Fill Station Radioalogical Requirements5001 Experimental Operation Radiological Requirements
5000 Tritium Fill Station Radiological Requirements(see also the preventive maintenance requirements for theCTHS System Description, Volume IV)
Radiological Requirement Reference PeriodicityRadiation Detection Instruments Femtotech U-24D Area Monitor Verify flow rate via rotameter Tech. Man. (¶6.1) M Device test Tech. Man. (¶6.1.2) W Vendor calibration Tech. Man. (¶4.5.3) A
Overhoff Tritium Air Samplers (2) (EPA Monitors) Replace/verify performance of catalytic oxidizer Inst. Manual A Calibrate constant flow controller Inst. Manual A Calibrate rotameter ASTM Procedure A
Overhoff Model 700 BAcC Portable Tritium Monitor Replace batteries Inst. Manual R, Q Vendor calibration Inst. Manual A
Ludlum Model 3 Portable Survey Meter with a Model 44-9 Detector Check batteries Inst. Manual R Replace batteries Inst. Manual R, Q Calibrate Inst. Manual A
Airborne Radiation Surveys Opening of glovebox Sec. 3003 R During decontamination procedures Sec. 3003 R (8 h) During DT piping/system maintenance Sec. 3003 R Room 150A during DT cart maintenance Sec. 3004 W Room 150B during condensate transfer Sec. 3004 R LaCave Lower Pylon (MCTC connect and Sec. 3004 R disconnect)
Part VMaintenance Procedures
Page V-215 August 2011
LLE Radiological Controls ManualPart V: Maintenance Procedures
LLE RADCONMANLLEINST 6610F
Surface Contamination Surveys Room 157 and anteroom Sec. 3004 W Room 2828 Sec. 3004 W Room 136 Decontamination area Sec. 3004 W Room 150A (Cart Maintenance Room) Sec. 3004 R Room 150B (Pump Room) Sec. 3004 R Upon removal of potentially tritiated components Sec. 3004 R Controlled surface contamination area Sec. 3004 R (4 h) Before, during, and after decontamination Sec. 3004 & 3009 R, R (8 h after) Sinks used for liquid disposal Sec. 3011 R
Liquid Activity Surveys Ultrasonic sinks during decontamination Sec. 3005 D TC-TRS condensate Sec. 3005 R Room 157 TRS condensate Sec. 3005 R TC-TRS chilled water Sec. 3005 R Room 157 TRS chilled water Sec. 3005 R CTHS DTHPS syringe pump oil Sec. 3005 RRadioactive Material Accountability Inventory and audit Sec. 3011 Q Liquid disposal report Sec. 3011 R
Personnel Monitoring Urinalysis testing Sec. 3013 R, W Smear testing Sec. 3004 & 3013
5001 Experimental Operation Radiological Requirements(see also the preventive maintenance procedures inOMEGA Operations Manual, Volume III)
Radiological Requirement Reference Periodicity
Radiation Detection Instruments Overhoff Model 700 BAcC Portable Tritium Monitor Replace batteries Inst. Manual R, Q Calibrate Inst. Manual A
Ludlum Model 3 Portable Survey Meter with a Model 44-9 Detector Check batteries Inst. Manual R Replace batteries Inst. Manual R, Q Calibrate Inst. Manual A
Ludlum Model 9 Ion Chamber Check/replace batteries Inst. Manual R Check/replace dessicant Inst. Manual Q Calibrate Inst. Manual A
Page V-315 August 2011
LLE Radiological Controls ManualPart V: Maintenance Procedures
LLE RADCONMANLLEINST 6610F
Wallac Model 1409 Liquid Scintillation Counter Count standard source using tritium protocol D Transfer data files W Back up system disk M Manufacturer’s service A
Perkin Elmer Tri-Carb 2910TR Count standard source using tritium protocol D Transfer data files D Manufacturer’s service A
Shielding Shielding effectiveness monitoring Sec. 3000 Q, R (1016 total n)
Target Bay Structure Activation Target Chamber activation Sec. 3001 S Target Bay general radiation Sec. 3002 S, R (1016 total n) R (1015 n/shot)Airborne Radiation Surveys Target Chamber entry Sec. 3008 & 3003 R Diagnostics that communicate with Target Chamber Sec. 3003 R Opening of other tritiated components Sec. 3003 R During decontamination procedures Sec. 3003 R (8 h)
Surface Contamination Surveys Target Chamber Entry Sec. 3008 & 3004 R Target Chamber Sec. 3004 S Target Bay Sec. 3004 S LaCave Sec. 3004 S Room 147 decontamination area Sec. 3004 W Target positioner and target storage area Sec. 3004 R Upon removal of potentially tritiated components Sec. 3004 R Controlled surface contamination area Sec. 3004 R (4 h) Potentially tritiated diagnostics Sec. 3004 M Before, during, and after decontamination Sec. 3004 & 3009 R, R (8 h after) Target Chamber alpha swipe (send to UR Q Radiological Safety)
Liquid Activity Surveys Ultrasonic sinks during decontamination Sec. 3005 D
Radioactive Material Accountability Inventory and audit Sec. 3011 Q
Personnel Monitoring Urinalysis testing Sec. 3013 W, R
Appendix A
Survey Maps, Logs, and Forms
LLEINST 6610F 15 August 2011
A-1–i
Radiation Shielding Monitoring Points Survey Map A-1
OMEGA Shield Point # Location 1 Experimental System Operation Station (Control Room) 2 Target/Laser Bay anteroom, south wall 3 Stairway opposite from Target Bay normal entrance door 4 Target Bay emergency exit, at foot of stairs on wall adjacent to LDL 5 Retired 6 Retired 7 Retired 8 Retired 9 Shaped-pulse damage testing facility, south wall/ceiling 10 LaCave Darkroom, east wall 11 Passageway between LaCave and Capacitor Bays on Capacitor Bay wall 12 Control Room, southwest corner 13 Rod Amplifier Room, east wall 14 Amplifier Test and Assembly Area, behind ultrasonic sink 15 Amplifier Test and Assembly Area, behind spare SSA storage area 16 Laser Bay, north wall (center) 17 Laser Bay, north wall (west) 18 Laser Bay, west wall (center near ceiling) 19 Retired 20 Laser Bay, south wall (east and low) OMEGA Shield Point # Location 21 LDL target area, south wall (east of target chamber) 22 LDL target area, south wall (middle of target chamber) 23 LDL target area, south wall (west of target chamber) 24 LDL target area, west wall 25 LDL target area, north wall 26 LDL target area, ceiling east side of chamber 27 Anteroom to target bay stairway south wall 28 OMEGA control room, under Shot Director’s desk
LLEINST 6610F 15 August 2011
A-1–ii
OMEGA EP Shield Point # Location 29 Adjacent to 4-ft × 4-ft beam hole in shield on OMEGA EP side (Prior to
OMEGA EP activation this will give OMEGA background after the OMEGA/OMEGA EP shield; after activation it will determine the necessity for OMEGA closed access due to OMEGA EP hard x rays.)
30 On the first landing of the OMEGA EP Viewing Gallery located at the approximate centerline of the OMEGA EP Target Chamber (In particular this will monitor for the 10-MeV x rays expected to be in a 45° cone and will determine the necessity to install up to 10 cm of lead shielding.)
31 Video Conference Room west end service corridor above electric panel near ceiling above the fire alarm enunciator (This will check hard-x-ray levels outside the 45° cone.)
32 EXOps Film Processing Room west wall near ceiling above fire alarm enunciator 33 EXOps Diagnostic Work Area in SW corner near ceiling on west wall by the door 34 Laser Bay entrance near Control Room on the back side of the curtain shield 35 Amplifier Assembly Area door to Laser Bay on the back side of the curtain shield 36 Optical Assembly Area door to Laser Bay on the back side of the curtain shield
(in NW corner of Rm. 6120) 37 South end on Laser Bay centerline on inside of shield wall 38 Diagnostics Bay below Target Chamber, center bay near ceiling on the north wall 39 North center Capacitor Bay on the north wall near the ceiling 40 Pump Room vestibule (fire exit from OMEGA Target Bay) on the east wall high
on the sealed door 41 OMEGA EP Mechanical Room east wall between AHU 2 and 5 high up near the
ceiling
LLEINST 6610F 15 August 2011
A-2–i
Target Bay Gamma Radiation Survey Map A-2a Target Bay Ground Level
Date: ___________________ Surveyed by: _____________________ All readings in mrem/h
N
G6526
G2:
G3:
C5:
C3:
C4:
C2:
C1:
G1:
Notes: (1) All readings in mrem/h (2) All “G” (general area) measurements are taken 30 cm from any structure and
averaged over a 360° sweep.
LLEINST 6610F 15 August 2011
A-2–ii
Target Bay Gamma Radiation Survey Map A-2b TMS Platform Level 1
Date: ___________________ Surveyed by: _____________________ All readings in mrem/h
N
G6527
C6:
C9:
G5:G4:
C7:
C8:
G5: 30 cm from equatorial plane of TC and 30 cm from any structure at that location.
LLEINST 6610F 15 August 2011
A-2–iii
Target Bay Gamma Radiation Survey Map A-2c TMS Platform Level 2
Date: ___________________ Surveyed by: _____________________ All readings in mrem/h
N
G6528
C10:
C13:
G7:
G6:
C12:
C11:
LLEINST 6610F 15 August 2011
A-3–i
OMEGA EP Target Bay Gamma Radiation Survey Map A-3a TAS Platform Level 1
Date: ___________________ Surveyed by: _____________________
G8306J1
G13:
C29:
C17:
G10: G9:
C15:
C16:
G11:
G8:
C14:
Notes: (1) All readings in mrem/h (2) All “G” (general area) measurements are taken 30 cm from any structure and
averaged over a 360° sweep.
LLEINST 6610F 15 August 2011
A-3–ii
OMEGA EP Target Bay Gamma Radiation Survey Map A-3b TAS Platform Level 2
Date: ___________________ Surveyed by: _____________________
G8307J1
C18:
G14:
G16:
C19:
C23:
G15:
C24:
C22:
G17:C21:
C20:
Notes: (1) All readings in mrem/h (2) All “G” (general area) measurements are taken 30 cm from any structure and
averaged over a 360° sweep.
LLEINST 6610F 15 August 2011
A-3–iii
OMEGA EP Target Bay Gamma Radiation Survey Map A-3c TAS Platform Level 3
Date: ___________________ Surveyed by: _____________________
G8308J1
G18:
C25:
G19:
C26:
G20:
C27:
C28:
G21:
Notes: (1) All readings in mrem/h (2) All “G” (general area) measurements are taken 30 cm from any structure and
averaged over a 360° sweep.
LLEINST 6610F 15 August 2011
A-3–iv
OMEGA EP Target Bay Gamma Radiation Survey Map A-3d Laser Bay Floor
Date: ___________________ Surveyed by: _____________________
G8309J1
G22:
G23:
TGATS
Notes: (1) All readings in mrem/h (2) All “G” (general area) measurements are taken 30 cm from any structure and
averaged over a 360° sweep.
Surface Contamination Survey Log (Wallac & Tri-Carb) LLEINST 6610F Survey Map A-4a 15 August 2011
Item/Area Surveyed: RMCL Number (if applicable):
Rack Position Number
S W I P E #
First S W I P E #
Intermediate S W I P E #
Post Decon S W I P E #
Final
DPM / 100 cm2
DPM / 100 cm2
DPM / 100 cm2
DPM / 100 cm2
1 BG BG BG BG 2 3 4 5 6 7 8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29
First Survey FILE Performed BY Date Intermediate FILE Performed BY Date Post Decon FILE Performed BY Date Final Survey FILE Performed BY Date
Surface Contamination Survey LogSurvey Map A-4b
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:File ID:
Item/Area Surveyed: Decontamination Area (LaCave)WipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKGG6529
Floor
Cap Bays
Table
Cabinets
XOPS storageshelf
5
2
1
3
4
To LaCaveTo elevatorContamination area
(LaCave)
Surface Contamination Survey Log Survey Map A-4c
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: LSC Area
G6530a
Tri-carbTable
Floor Darkroom
LaCave
To Target Bay
5
2
1
34
WipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
File ID:
Surface Contamination Survey LogSurvey Map A-4d
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: Micro Assembly Lab, Room 2828WipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
G6531
File ID:
Surface Contamination Survey LogSurvey Map A-4e
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: Tritium FacilityWipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
G6532J1
TFS
glov
ebox
TGC
CharacterizationstationNo. 1
FTSNo. 1
TRSPump
FTS
No. 2
FTS-1 desk FTS-2 desk TRS desk
CharacterizationstationNo. 2
Key:F = FloorG = GloveS = SurfaceO = Other(Specify)
Hood
File ID:
Surface Contamination Survey LogSurvey Map A-4f
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: OMEGA Target Bay–Ground LevelWipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
G6533
N
#6
#1
#7
#3
#2
#4
#5
File ID:
Surface Contamination Survey LogSurvey Map A-4g
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: OMEGA Target Bay–TMS Platform Level 1WipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
G6534
N
#10(H7)
#8(H14)
#9
File ID:
Surface Contamination Survey LogSurvey Map A-4h
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: OMEGA Target Bay–TMS Platform Level 2WipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
G6535
N
#11(P1 Stairs)
#12Console shelf
#13
File ID:
Surface Contamination Survey LogSurvey Map A-4i
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: Target Positioner 2WipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKGG6536
3
6
8
9
11
7
15
4
2
10
1. Touchscreen2. North side shelf3. North side of web4. TPS-2 gate valve5. TPS-2 handles6. Bottom of web7. TPS-2 door8. South side of web9. South side shelf10. Target storage box11. Target bottle storage rackPlease note any additional swipe locations if needed.
File ID:
Surface Contamination Survey LogSurvey Map A-4j
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: LaCave DarkroomWipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKGG6537
1. Darkroom �oor2. Film drop-off shelf3. Film pickup shelf4. Dry darkroom work table5. Film-labeling counter6. Door handle
Filmdrier
Jobo 1
Jobo 2
Jobo 3
41
2
3
5
6
File ID:
Surface Contamination Survey LogSurvey Map A-4k
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: LaCaveWipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
File ID:
G6538bJ2
Consult “LaCave ContaminationArea Survey Map”
Cryostatdoorway
N
1. Beneath spools2. In front of MCTC parking lot3. MCTC staging area
1
2
Spool 5
45
3
Surface Contamination Survey LogSurvey Map A-4l
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: Decontamination Area Room 136WipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKGG6539
Shelves
Counter
Counter
CabinetEntry
Sink
File ID:
Surface Contamination Survey LogSurvey Map A-4m
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: Cart Maintenance Room (Room 150A)WipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
G6540
File ID:
Surface Contamination Survey Log Survey Map A-4n
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:
Item/Area Surveyed: Pump House/TC-TRS (Room 150B)WipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
G6541
File ID:
Surface Contamination Survey LogSurvey Map A-4o
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:File ID:
Item/Area Surveyed: Room 157 HoodWipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
G7548J1
Glass
Backsplash WallWall
Floor
Sill
Surface Contamination Survey LogSurvey Map A-4p
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:File ID:
Item/Area Surveyed: TC-TRS Condensate TransferWipeNo.
RackPosition
dpm/100 cm2
Background 12345678910111213141516171819202122232425262728
co*cktail BKG
G7587J1
Receiving container
Pipette
3/4”wrench
Screwdriver
5/8”wrench
Floor in front of T-8701
T-8701
HV-8712
Samplingport
HV-8711HV-
8710
HV-8713 P-8710
HV-8707
LLEINST 6610F 15 August 2011
Wallac Liquid Scintillation Counter Log Book Survey Log A-1: Surface Contamination Survey Log for Clean Items
NOTE: This log sheet is for items surveyed and found to be “CLEAN.” Log highest “clean” reading.
Date Time File ID Item Surveyed Highest Reading Name
Liquid Activity Survey LogSurvey Log A-2
LLEINST 6610F15 August 2011
RMCL Number (If applicable):________________
Date:SurveyPerformed by:Final:Intermediate:In Process:Initial:File ID:
Item/Area Surveyed: Cryo and Tritium Facility Water Condensate
Sample # Rack Position #
Pipet Volume (nL)
(1 ml = 1000 nL)
Wallac dpm Reading (dpm)
Dilution Factor1000/Pipet
Volume
Activity (dpm/ml)
Wallac Reading # Dilution Factor
Control 1 1000 12345678910111213141516171819202122232425
Source of water
CHECK ONE OF THE FOLLOWING:
❏ TC-TRS T-8701 (Regen Condensate Tank)
❏ Room 157 TRS T-8801 (Regen Condensate Tank)
❏ TC-TRS Chilled Water Loop
❏ Room 157 TRS Chilled Water Loop
❏ DTHPS Glovebox Chilled Water Loop
❏ Other (specify): __________________
LLEINST 6610F 15 August 2011
Liquid Activity Survey Log Survey Log A-3
Sample Location Sample Type Rack No. dpm/ml Time/Date Performed by Disposition
LLEINST 6610F 15 August 2011
Airborne Radiation Survey Log Survey Log A-4
Airborne Radiation Survey Survey Location Inst. used Level (µCi/m3) Time/date Performed by
LLEINST 6610F 15 August 2011
Target Chamber Personnel and Material Entry Log Log A-4
Personnel Entry Date Time Time Time Time Name In Out Name In Out Material Entry Time Time Material description In Out Explanation if material left in
LLEINST 6610F 15 August 2011
Radioactive Material Control Log
Log A-5
Tag # Inception
Date Entered Into RMCL by:
Material Description Isotope
Activity (µCi/100 cm2) Location Disposition
Removed from RMCL by:
3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H 3H * e.g., Transferred to UR Radiation Safety (xfer-UR RS); decontaminated/released (decon); reinstalled on system (install.)
LLEINST 6610F 15 August 2011
Weekly Radiological Survey Cover Sheet — Target Production Log A-6
Period _____________ to _____________
(date) (date)
Refer to LLE Instruction 6610F – Log A-7
For daily calibration data of liquid scintillation counters
Log Sheets Attached: Airborne Radiation Surveys pages Surface Contamination Surveys pages Liquid Activity Surveys pages
Remarks: Submitted/Reviewed: / OMEGA Facility Director Date
Reviewed: / LLE Radiation Safety Office Date
LLEINST 6610F LLEINST 6610F
15 August 2011
Weekly Radiological Survey Cover Sheet Experimental Operations Group
Log A-7 Period ____________ to ____________ (date) (date)
Tri-Carb 2910TR/Overhoff TASC Daily Calibration Check: 3H Chi Square
must be >7.5 and <36.2
3H E2/B must be >400 and <560
3H Background must be
<11 CPM
File Name (MMDDYYHHMM)
Date Time EPA Heater
On
EPA Sample Flow
(cc/min)
Indicated Stack Flow
(CFM)
Wallac 1409/Overhoff TASC Daily Calibration Check: (std: 195400 DPM) Measured
DPM of Std. (DPMactual)
% Error 100*(DPMactual-DPMstd)
(DPMstd) MUST BE <5%
Output File Name
Log Sheets Attached: Report # Surveys Remarks: EPA Compliance Monitor Report Surface Contamination Surveys Airborne Activity Surveys Liquid Activity Surveys Submitted/Reviewed: / Experimental Operations Group Leader Date Reviewed: / LLE Radiation Safety Officer Date
LLEINST 6610F 15 August 2011
Target Chamber Access Authorization Form A-1
Reason for entry: Entry requested by: Time/date Access Authorized by1: Time/date Entry checklist: Controlled Surface Contamination Area established Target Chamber vented to atmosphere and purged for 4 hours Target Chamber vacuum control tagged out Cryopump gate valve air supply closed and tagged out Verify beam-transfer tube is vented to atmosphere Control Point Watch stationed Airborne radiation survey of Target Chamber <20 µCi/m3 (2 × 10−5) and logged Surface contamination of area around entrance hatch taken and logged If surface contamination at entrance is >10,000 DPM/100 cm2, additional anticontamination clothing per section 3006 is donned. Complete surface contamination survey of Target Chamber completed and logged prior to granting general access Personnel entering are qualified as Radiation Workers and have been fitted for and will use respirators. Special Requirements for entry: Closeout checklist: Target Chamber inspected—no personnel or tools or material left inside Access cover closed Personnel access and tool log reviewed to ensure everything accounted for Radioactive Material properly packaged for transfer to UR Radiation Safety Controlled Surface Contamination Area collapsed Report Target Chamber closed to Shot Director Remove tag from vacuum control Remove tag from cryopump gatevalve air supply 1 The Shot Director must also obtain verbal permission from the LLE Radiation Safety Officer
prior to granting authorization.
LLEINST 6610F 15 August 2011
LLE TFS, CTHS, OMEGA Tritium Inventory Form A-2
Instructions: 1. Copy entire last line to the empty row below it. 4. Enter the amount, if any, that was either (a) received into column B or (b) transferred out into column F. 2. Enter date in column A. 5. Enter a description of the activity in column J. 3. If an assay was measured, enter the value into column C; if not measured, 6. Report to LLE RSO if the computed variance in column I exceeds 5%. use estimated value in column D.
A B C D E F G H I J Date Received
(Ci) Measured USB
Inventory (Ci)
Calculated USB Activity
(Ci)
Calculated System Activity
(Ci)
Transfer Off-Site
Decay Corrected TOTAL
Inventory (Ci)
Calculated TOTAL
Inventory Decayed (Ci)
Variance % Difference
between E and G
Comments
Note that TOTAL inventory = USB inventory + System. *The long-term accuracy of the TFS assay is ±2%. D = Decay corrected previous column C H = Amount that previous column G decayed E = Difference between column G and column C I = 100% × (column G–column E)/(column G) G = Decay corrected previous column G + current column B – current column F
LLEINST 6610F 15 August 2011
Warm Tritium Target Inventory Form A-3
Current Date:
Batch Title
Gas Fill (atm)
Comments Number of
Targets
Total Activity Without Decay
(mCi)
Elapsed Time (mCi)
Corrected Activity (mCi)
Fill Date
Campaign or
Date Total
Appendix B
Definitions
LLEINST 6610F 15 August 2011
B-i
APPENDIX B: DEFINITIONS
Absorbed dose is the energy imparted by ionizing radiation per unit mass of irradiated material. The units of absorbed dose are the gray (Gy) and the rad.
Activity is the rate of disintegration or transformation or decay of radioactive material. The units of activity are the becquerel (Bq) and the curie (Ci).
Agreement State is any State with which the United States Nuclear Regulatory Commission or the United States Atomic Energy Commission has entered into an effective agreement under Section 274b of the Atomic Energy Act of 1954, as amended (73 Stat. 689).
Airborne radioactive material is any radioactive material dispersed in the air in the form of dusts, fumes, particulates, mists, vapors, or gases.
Annual limit on intake (ALI) is the derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by the reference man that would result in a committed effective dose equivalent of 0.05 Sv (5 rem) or a committed dose equivalent of 0.5 SV (50 rem) to any individual organ or tissue.
As low as is reasonably achievable (ALARA) means making every reasonable effort to maintain exposures to radiation as far below the dose limits in these regulations as is practical, consistent with the purpose for which the licensed or registered activity is undertaken, taking into account the state of technology, the economics of improvements in relation to state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and licensed or registered sources of radiation in the public interest.
Background radiation means radiation from cosmic sources; naturally occurring radioactive materials, including radon, except as a decay product of source or special nuclear material, and including global fallout as it exists in the environment from the testing of nuclear explosive devices.
Becquerel (Bq) is the SI unit of activity. One becquerel is equal to one disintegration or transformation per second (s−1).
Bioassay means the determination of kinds, quantities or concentrations, and, in some cases, the locations of radioactive material in the human body, whether by direct measurement, in vivo counting, or analysis and evaluation of materials excreted or removed from the human body. For purposes of these regulations, “radiobioassay” is an equivalent term.
Calibration means the determination of
– the response or reading of an instrument relative to a series of known radiation values over the range of the instrument, or
– the strength of a source of radiation relative to a standard.
CFR means Code of Federal Regulations.
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Committed dose equivalent (HT,50) is the dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive materials by an individual during the 50-year period following the intake.
Committed effective dose equivalent (HE,50) is the sum of the products of the weighing factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to each of these organs or tissues (HE,50 = Σ WT HT,50).
Controlled area means any area the access to which is controlled for the purpose of protecting individuals from exposure to radiation and radioactive material, but shall not mean any area used as residential quarters.
Curie is a unit of activity. One curie (Ci) is that quantity of radioactive material that decays at the rate of 3.7 × 1010 transformations per second (tps).
Deep dose equivalent (Hd), which applies to external whole body exposure, is the dose equivalent at a tissue depth of 1 cm (1000 mg/cm2).
Derived air concentration (DAC) is the concentration of a given radionuclide in air that, if breathed by the reference man for a working year of 2000 hours under conditions of light work, results in an intake of one ALI. For purposes of these regulations, the condition of light work is an inhalation rate of 1.2 cubic meters of air per hour for 2000 hours in a year.
Dose is a generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equivalent, committed effective dose equivalent, or total effective dose equivalent. For purposes of these regulations, “radiation dose” is an equivalent term.
Dose equivalent (HT) is the product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest. The units of dose equivalent are the sievert (Sv) and rem.
Dose limits are the permissible upper bounds of radiation doses established in accordance with these regulations. For purposes of these regulations, “limits” is an equivalent term.
Effective dose equivalent (HE) is the sum of the products of the dose equivalent to each organ or tissue (HT) and the weighting factor (WT) applicable to each of the body organs or tissues that are irradiated (HE = Σ WT HT).
Entrance or access point is any opening through which an individual or extremity of an individual could gain access to radiation areas or to licensed or registered radioactive materials. This includes entry or exit portals of sufficient size to permit human entry, irrespective of their intended use.
Exposure means either:
– being exposed to ionizing radiation or to radioactive material; or
– the quotient of dQ by dm where “dQ” is the absolute value of the total charge of the ions of one sign produced in air when all the electrons (negatrons and positrons) liberated by photons in a volume element of air having mass “dm” are completely stopped in air. The special unit of exposure is the roentgen (R). One roentgen is equal to 2.58 × 10−4 coulomb per kilogram of air.
Exposure rate is the exposure per unit of time, such as roentgen per minute and milliroentgen per hour.
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External dose is that portion of the dose equivalent received from any source of radiation outside the body.
Extremity means hand, elbow, arm below the elbow, foot, knee, and leg below the knee.
Gray (Gy) is the SI unit of absorbed dose. One gray is equal to an absorbed dose of 1 J/kg. One gray is equal to 100 rad.
High-radiation area is any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 1 mSv (0.1 rem) in 1 hour at 30 cm from any source of radiation or from any surface that the radiation penetrates. For purposes of these regulations, rooms or areas in which diagnostic x-ray systems are used for healing arts purposes are not considered high-radiation areas.
Individual monitoring means the assessment of
Dose equivalent: – by the use of individual monitoring devices or – by the use of survey data; or Committed effective dose equivalent: – by bioassay or – by determination of the time-weighted air concentrations to which an individual has been
exposed, that is, DAC-hours.
Individual (personnel) monitoring devices are devices designed to be worn by a single individual for the assessment of dose equivalent. For purposes of these regulations, individual monitoring equipment and personnel monitoring equipment are equivalent terms. Examples of individual monitoring devices are film badges, thermoluminescent dosimeters (TLD’s), pocket dosimeters, and personal air-sampling devices.
Internal dose is that portion of the dose equivalent received from radioactive material taken into the body.
License means a radioactive material license issued by the NYS Department of Health in accordance with the regulations adopted by the Department.
Licensed material means radioactive material received, possessed, used, transferred, or disposed of under a general or specific license issued by the NYS Department of Health.
Monitoring is the measurement of radiation, radioactive material concentrations, surface area activities or quantities of radioactive material and the use of the results of these measurements to evaluate potential exposure and doses.
Occupational dose is the dose received by an individual in the course of employment in which the individual’s assigned duties involve exposure to sources of radiation, whether in the possession of the licensee, registrant, or other person. Occupational dose does not include doses received: from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.
Quality factor (Q) is the modifying factor that is used to derive dose equivalent from absorbed dose.
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– As used in these regulations, the quality factors for converting absorbed dose to dose equivalent are shown in Table I.
TABLE I
QUALITY FACTORS AND ABSORBED DOSE EQUIVALENTS
Type of Radiation
Quality Factor
(Q)
Absorbed Dose Equal to a Unit Dose Equivalenta
X, gamma, or beta radiation and high-speed electrons
1
1
Alpha particles, multiple-charged particles, fission fragments, and heavy particles of unknown charge
20
0.05 Neutrons of unknown energy 10 0.1 High-energy protons 10 0.1 aAbsorbed dose in rad equal to 1 rem or the absorbed dose in gray equal to 1 Sv.
Rad is the non-SI unit of absorbed dose. One rad is equal to an absorbed dose of 100 erg/gram or 0.01 J/kg (0.01 gray). One millirad equals 0.001 rad.
Radiation means alpha particles, beta particles, gamma rays, x rays, neutrons, high-speed electrons, high-speed protons, and other particles capable of producing ions. Ionizing radiation is an equivalent term. Radiation does not include nonionizing radiation, such as radiowaves or microwaves, visible, infrared, or ultraviolet light.
Radiation area is any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 0.05 mSv (0.005 rem) in 1 hour at 30 cm from the source of radiation or from any surface that the radiation penetrates.
Radiation source is any radioactive material or any radiation equipment.
Radioactive material is any solid, liquid, or gas which emits radiation spontaneously.
Radioactivity is the transformation of unstable atomic nuclei by the emission of radiation.
Reference man means a hypothetical aggregation of human physical and physiological characteristics determined by international consensus. These characteristics may be used by researchers and public health workers to standardize results of experiments and to relate biological insult to a common base.
Rem is the unit of dose equivalent. The dose equivalent in rem is equal to the absorbed dose in rad multiplied by the quality factor (1 rem = 0.01 sievert).
Respiratory protective equipment means an apparatus, such as a respirator, used to reduce an individual’s intake of airborne radioactive material.
Roentgen is the unit of exposure. One roentgen (R) equals 2.58 × 10−4 coulombs/kilogram of air (see Exposure).
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Sanitary sewerage means a system of public sewers for carrying off waste and refuse, but excluding sewage treatment facilities, septic tanks, and leach fields owned or operated by the licensee or registrant.
Sealed source means radioactive material that is permanently bonded or fixed in a capsule or matrix designed to prevent release and dispersal of the radioactive material under the most severe conditions that are likely to be encountered in normal use and handling.
Shallow dose of equivalent (Hs), which applies to the external exposure of the skin or an extremity, is the dose equivalent at a tissue depth of 0.007 cm (7 mg/cm2) averaged over an area of 1 sq cm.
Sievert is the SI unit of dose equivalent. The dose equivalent in sievert is equal to the absorbed dose in gray multiplied by the quality factor (1 Sv = 100 rem).
Source of radiation means any radioactive material or any device or equipment emitting, or capable of producing, radiation.
Survey means an equivalent of the radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of sources of radiation. When appropriate, such evaluation includes, but is not limited to, tests, physical examinations, and measurements of levels of radiation or concentrations of radioactive material present.
Total effective dose equivalent (TEDE) is the sum of the deep dose equivalent for external exposures and the committed effective dose equivalent for internal exposures.
Weighting factor (WT) for an organ or tissue (T) means the proportion of the risk of stochastic effects resulting from irradiation of that organ or tissue to the total risk of stochastic effects when the whole body is irradiated uniformly. For calculating the effective dose equivalent, the values of WT are as follows:
Organ Dose Weighting Factors
Organ or Tissue WT Gonads 0.25 Breast 0.15 Red Bone Marrow 0.12 Lung 0.12 Thyroid 0.03 Bone Surfaces 0.03 Remainder 0.30(a) Whole Body 1.00(b)
(a)0.30 results from 0.06 for each of five “remainder” organs, excluding the skin and the lens of the eye, that receive the highest doses.
(b)For purposes of weighting the external whole body dose, for adding it to the internal dose, a single weighting factor, WT = 1.0, has been specified. The use of other weighting factors for external exposure will be approved on a case-by-case basis until such time as specific guidance is issued.
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Whole body means, for purposes of external exposure, head, trunk (including male gonads), arms above the elbow, or legs above the knee.
Worker means an individual engaged in work under a license or registration issued by the NYS Department of Health and controlled by a licensee or registrant, but does not include the licensee or registrant.
Appendix C
Acronyms & Abbreviations
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APPENDIX C: ACRONYMS & ABBREVIATIONS
Α annual α alpha (radiation) Ag silver ALARA as low as reasonably achievable ALI Annual Limit on Intake Ar argon atm atmosphere β beta (radiation) Bq becquerel cc cubic centimeters CFR Code of Federal Regulations Ci curie cm centimeter CPM counts per minute CTHS Cryogenic Target Handing System D diameter or deuterium or daily maintenance requirement DAC derived air concentration DD deuterium–deuterium DEC Department of Environmental Conservation DOH Department of Health dpm disintegrations per minute DT deuterium–tritium DTHPS DT high pressure system EP Extended Performance EPA Environmental Protection Agency eV electron volts FASP Stage-F Alignment Sensor Package Fe iron ft foot γ gamma (radiation) Gy gray h hour H hydrogen He helium HE effective dose equivalent HS shallow dose equivalent HT hydrogen–tritium (gaseous molecule)
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HT dose equivalent HTO hydrogen–tritium oxide (tritiated water) ICF inertial confinement fusion ICRP International Conference on Radiation Protection in. inch J joule keV kilo electron volts kg kilogram kPa kilopascal Kr krypton LFORM Laser Facility Operations & Regulation Manual LLNL Lawrence Livermore National Laboratory m meters M monthly mCi millicuries MeV million electron volts Mg magnesium mg milligram ml milliliter Mn manganese mR milliroentgen mrem millirem mSv millisieverts n neutron N nitrogen Na sodium NYCRR New York Code of Rules and Regulations NYS New York State O oxygen OD outside diameter p proton Pb lead Pd palladium Q quality factor or quarterly maintenance requirement r radius R Roentgen or situational maintenance requirement rad special unit of absorbed radiation rem roentgen equivalent man s second S semiannual
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scfm standard cubic feet per minute sq square Sv Sievert T tritium TEDE total effective dose equivalent TFS Tritium Fill Station TLD thermoluminescent dosimeter TP target positioner TRS tritium removal system µCi microcuries µrem micro rem UR University of Rochester W weekly WT weighting factor yr year Zr zirconium