Rad Data Handbook 20.. - Voss Associates

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Photon Shielding Buildup Factors MeV Water Aluminum Concrete Iron Lead 0.5 2.52 2.37 2.19 1.98 1.24 1.0 2.13 2.02 1.94 1.87 1.37 2.0 1.83 1.75 1.75 1.76 1.39 Neutron and Gamma Shielding SIMPLIFIED SHIELD THICKNESS CALCULATION perform radiation measurements to verify these calculations I = shielded exposure rate I 0 = unshielded exposure rate n = number of shielding layers (tenth or half) I = I 0 x 0.1 n for tenth value thickness I = I 0 x 0.5 n for half value thickness Radiation Streaming Consider the potential for radiation streaming thru gaps in the shielding. Design the shielding to minimize gaps and perform a comprehensive survey after the shielding is in place. Stay-Time Calculation Stay-time calculations are typically used to determine how long an individual can remain in an area with elevated radiation fieldsu ntil they reach some pre-determined dose limit. The principles can also be applied to airborne areas. Stay-time = Allowable exposure/exposure rate example; allowable exposure is 100 mR exposure rate is 25 mR/hr Stay-time = 100 mR / 25 mR/hr = 4 hours 54 Photon Shielding Buildup Factors MeV Water Aluminum Concrete Iron Lead 0.5 2.52 2.37 2.19 1.98 1.24 1.0 2.13 2.02 1.94 1.87 1.37 2.0 1.83 1.75 1.75 1.76 1.39 Neutron and Gamma Shielding SIMPLIFIED SHIELD THICKNESS CALCULATION perform radiation measurements to verify these calculations I = shielded exposure rate I 0 = unshielded exposure rate n = number of shielding layers (tenth or half) I = I 0 x 0.1 n for tenth value thickness I = I 0 x 0.5 n for half value thickness Radiation Streaming Consider the potential for radiation streaming thru gaps in the shielding. Design the shielding to minimize gaps and perform a comprehensive survey after the shielding is in place. Stay-Time Calculation Stay-time calculations are typically used to determine how long an individual can remain in an area with elevated radiation fieldsu ntil they reach some pre-determined dose limit. The principles can also be applied to airborne areas. Stay-time = Allowable exposure/exposure rate example; allowable exposure is 100 mR exposure rate is 25 mR/hr Stay-time = 100 mR / 25 mR/hr = 4 hours 54 Photon Shielding Buildup Factors MeV Water Aluminum Concrete Iron Lead 0.5 2.52 2.37 2.19 1.98 1.24 1.0 2.13 2.02 1.94 1.87 1.37 2.0 1.83 1.75 1.75 1.76 1.39 Neutron and Gamma Shielding SIMPLIFIED SHIELD THICKNESS CALCULATION perform radiation measurements to verify these calculations I = shielded exposure rate I 0 = unshielded exposure rate n = number of shielding layers (tenth or half) I = I 0 x 0.1 n for tenth value thickness I = I 0 x 0.5 n for half value thickness Radiation Streaming Consider the potential for radiation streaming thru gaps in the shielding. Design the shielding to minimize gaps and perform a comprehensive survey after the shielding is in place. Stay-Time Calculation Stay-time calculations are typically used to determine how long an individual can remain in an area with elevated radiation fieldsu ntil they reach some pre-determined dose limit. The principles can also be applied to airborne areas. Stay-time = Allowable exposure/exposure rate example; allowable exposure is 100 mR exposure rate is 25 mR/hr Stay-time = 100 mR / 25 mR/hr = 4 hours 54 Photon Shielding Buildup Factors MeV Water Aluminum Concrete Iron Lead 0.5 2.52 2.37 2.19 1.98 1.24 1.0 2.13 2.02 1.94 1.87 1.37 2.0 1.83 1.75 1.75 1.76 1.39 Neutron and Gamma Shielding SIMPLIFIED SHIELD THICKNESS CALCULATION perform radiation measurements to verify these calculations I = shielded exposure rate I 0 = unshielded exposure rate n = number of shielding layers (tenth or half) I = I 0 x 0.1 n for tenth value thickness I = I 0 x 0.5 n for half value thickness Radiation Streaming Consider the potential for radiation streaming thru gaps in the shielding. Design the shielding to minimize gaps and perform a comprehensive survey after the shielding is in place. Stay-Time Calculation Stay-time calculations are typically used to determine how long an individual can remain in an area with elevated radiation fieldsu ntil they reach some pre-determined dose limit. The principles can also be applied to airborne areas. Stay-time = Allowable exposure/exposure rate example; allowable exposure is 100 mR exposure rate is 25 mR/hr Stay-time = 100 mR / 25 mR/hr = 4 hours 54
Beta Dose Rates in rad/hr per mCi MeV 1 cm 10 cm 30 cm 60 cm 90 cm 1.0 m 0.15 1,200 1.7 0 0 0 0 0.25 1,000 2.2 0.1 0 0 0 0.30 900 3.6 0.1 0 0 0 0.50 750 5.2 0.4 0.05 0.01 0 0.75 650 5.0 0.5 0.05 0.01 0 1.0 550 4.6 0.4 0.1 0 0 1.25 450 4.3 0.4 0.1 0.04 0.02 1.50 400 4.0 0.4 0.1 0.04 0.02 1.75 350 3.4 0.4 0.1 0.04 0.02 2.00 340 3.6 0.4 0.1 0.04 0.02 2.25 320 3.3 0.4 0.1 0.04 0.02 Beta dose should be treated as a “shallow” dose and should not be summed with “deep” doses. This chart should also be used to determine beta+ doses from positron emitters. Half-value Thickness vs Beta Energy Isotope Emax (MeV) Half-Value Thickness mg / cm 2 C-14 0.156 2 Tc-99 0.292 7.5 Cl-36 0.714 15 Sr/Y-90 0.546 / 2.284 150 U-238 Betas from short lived progeny 0.191 / 2.281 130 P-32 1.710 150 Estimate the half-value thickness for a beta emitter. mg/cm 2 = 50 x E 2 where E is Emax in MeV for the beta emitter This equation tends to underestimate the half-value thickness for low energy betas and overestimate the half-value thickness for high energy betas. Beta Dose Rates in rad/hr per mCi MeV 1 cm 10 cm 30 cm 60 cm 90 cm 1.0 m 0.15 1,200 1.7 0 0 0 0 0.25 1,000 2.2 0.1 0 0 0 0.30 900 3.6 0.1 0 0 0 0.50 750 5.2 0.4 0.05 0.01 0 0.75 650 5.0 0.5 0.05 0.01 0 1.0 550 4.6 0.4 0.1 0 0 1.25 450 4.3 0.4 0.1 0.04 0.02 1.50 400 4.0 0.4 0.1 0.04 0.02 1.75 350 3.4 0.4 0.1 0.04 0.02 2.00 340 3.6 0.4 0.1 0.04 0.02 2.25 320 3.3 0.4 0.1 0.04 0.02 Beta dose should be treated as a “shallow” dose and should not be summed with “deep” doses. This chart should also be used to determine beta+ doses from positron emitters. Half-value Thickness vs Beta Energy Isotope Emax (MeV) Half-Value Thickness mg / cm 2 C-14 0.156 2 Tc-99 0.292 7.5 Cl-36 0.714 15 Sr/Y-90 0.546 / 2.284 150 U-238 Betas from short lived progeny 0.191 / 2.281 130 P-32 1.710 150 Estimate the half-value thickness for a beta emitter. mg/cm 2 = 50 x E 2 where E is Emax in MeV for the beta emitter This equation tends to underestimate the half-value thickness for low energy betas and overestimate the half-value thickness for high energy betas. Beta Dose Rates in rad/hr per mCi MeV 1 cm 10 cm 30 cm 60 cm 90 cm 1.0 m 0.15 1,200 1.7 0 0 0 0 0.25 1,000 2.2 0.1 0 0 0 0.30 900 3.6 0.1 0 0 0 0.50 750 5.2 0.4 0.05 0.01 0 0.75 650 5.0 0.5 0.05 0.01 0 1.0 550 4.6 0.4 0.1 0 0 1.25 450 4.3 0.4 0.1 0.04 0.02 1.50 400 4.0 0.4 0.1 0.04 0.02 1.75 350 3.4 0.4 0.1 0.04 0.02 2.00 340 3.6 0.4 0.1 0.04 0.02 2.25 320 3.3 0.4 0.1 0.04 0.02 Beta dose should be treated as a “shallow” dose and should not be summed with “deep” doses. This chart should also be used to determine beta+ doses from positron emitters. Half-value Thickness vs Beta Energy Isotope Emax (MeV) Half-Value Thickness mg / cm 2 C-14 0.156 2 Tc-99 0.292 7.5 Cl-36 0.714 15 Sr/Y-90 0.546 / 2.284 150 U-238 Betas from short lived progeny 0.191 / 2.281 130 P-32 1.710 150 Estimate the half-value thickness for a beta emitter. mg/cm 2 = 50 x E 2 where E is Emax in MeV for the beta emitter This equation tends to underestimate the half-value thickness for low energy betas and overestimate the half-value thickness for high energy betas. Beta Dose Rates in rad/hr per mCi MeV 1 cm 10 cm 30 cm 60 cm 90 cm 1.0 m 0.15 1,200 1.7 0 0 0 0 0.25 1,000 2.2 0.1 0 0 0 0.30 900 3.6 0.1 0 0 0 0.50 750 5.2 0.4 0.05 0.01 0 0.75 650 5.0 0.5 0.05 0.01 0 1.0 550 4.6 0.4 0.1 0 0 1.25 450 4.3 0.4 0.1 0.04 0.02 1.50 400 4.0 0.4 0.1 0.04 0.02 1.75 350 3.4 0.4 0.1 0.04 0.02 2.00 340 3.6 0.4 0.1 0.04 0.02 2.25 320 3.3 0.4 0.1 0.04 0.02 Beta dose should be treated as a “shallow” dose and should not be summed with “deep” doses. This chart should also be used to determine beta+ doses from positron emitters. Half-value Thickness vs Beta Energy Isotope Emax (MeV) Half-Value Thickness mg / cm 2 C-14 0.156 2 Tc-99 0.292 7.5 Cl-36 0.714 15 Sr/Y-90 0.546 / 2.284 150 U-238 Betas from short lived progeny 0.191 / 2.281 130 P-32 1.710 150 Estimate the half-value thickness for a beta emitter. mg/cm 2 = 50 x E 2 where E is Emax in MeV for the beta emitter This equation tends to underestimate the half-value thickness for low energy betas and overestimate the half-value thickness for high energy betas.
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Abbreviations 115 Activity vs Expos
Page 3 and 4:
RADIOLOGICAL EMERGENCY RESPONSE Wri
Page 5 and 6: HAZARD CONTROL PRIORITIES DURING ME
Page 7 and 8: ACUTE RADIATION EFFECTS 0 - 25 REM
Page 9 and 10: TABLE OF THE ELEMENTS Z Density Z D
Page 11 and 12: Relative Locations of Products of N
Page 13 and 14: RADIOACTIVE DECAY MODES OF COMMONLY
Page 15 and 16: Progeny kev and % abundance 55 Fe 5
Page 17 and 18: Progeny kev and % abundance 99 Mo 9
Page 19 and 20: Progeny kev and % abundance 208 Tl
Page 21 and 22: Progeny kev and % abundance 229 Th
Page 23 and 24: Progeny kev and % abundance 241 Am
Page 25 and 26: Progeny kev and % abundance Progeny
Page 27 and 28: Progeny kev and % abundance 222 Rn
Page 29 and 30: Neptunium Decay Chain (4n + 1) st 1
Page 31 and 32: Actinium Decay Chain (4n + 3) st 1
Page 33 and 34: Ci / g = 3.578E5 / (T 1/2 in years
Page 35 and 36: Rem/hr / Ci Sv/hr / GBq Half-Life C
Page 45 and 46: mRem/hr mSv/hr 1ì 10ì 100ì 1ì 1
Page 47 and 48: RADIATION BIOLOGY Maximum survivabl
Page 49 and 50: INTERNAL DOSIMETRY Calculating CDE
Page 51 and 52: EQUIVALENT DOSE, EFFECTIVE DOSE, an
Page 53 and 54: CALCULATING TODE AND TEDE TEDE = DD
Page 55: SHIELDING MATERIALS α a single she
Page 59 and 60: Combining Radiation Types to Determ
Page 61 and 62: NEUTRON SHIELD THICKNESS I = I0e -N
Page 63 and 64: Exposure Rate in an Air-Filled Ion
Page 65 and 66: Inverse Square Law 2 2 X 1 (D) 1 =
Page 67 and 68: Table 1 of DOE 5400.5 Surface Activ
Page 69 and 70: 6CEN The 6CEN equation can be used
Page 71 and 72: Ventilation Rates Ventilation rates
Page 73 and 74: AIR FLOW METER CORRECTIONS Mass Flo
Page 75 and 76: 10CFR20 DAC 10CFR835 DAC 10CFR20 AL
Page 103 and 104: External Exposure in a Cloud of Air
Page 105 and 106: Characteristic X-Rays (KeV) of the
Page 107 and 108:
Z # K K L L 103 Lr 71 Lu 54.06 61.2
Page 109 and 110:
COUNTING STATISTICS COUNTING STATIS
Page 111 and 112:
ELEVATION VS AIR PRESSURE Barometri
Page 113 and 114:
NE Omaha 983 UT Cedar City 5,623 NH
Page 115 and 116:
COMPOSITION OF AIR Density of Symbo
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ABBREVIATIONS ampere A, or amp angs
Page 119 and 120:
Mass 1 gram = 0.03527 ounces 1 ounc
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Radiological 1 BTU = 235 1.28E-8 g
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CONSTANTS Avogadro's number (N 0) 6
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ELECTROMAGNETIC SPECTRUM Wavelength
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5. Air-proportional alpha detectors
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32 7. The bremsstrahlung from a 1 C
Page 131 and 132:
RULES OF THUMB FOR NEUTRONS 1. The
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Spontaneous Fission Neutron and Gam
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Energy & Yield of neutrons from the
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WG Pu 15 years after fabrication 23
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Isotopic Mix of Natural U 238 U 234
Page 141 and 142:
MISCELLANEOUS RULES OF THUMB 1. One
Page 143 and 144:
PUBLIC RADIATION DOSES Average per
Page 145 and 146:
COMPARATIVE RISKS OF RADIATION EXPO
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Voss Associates provides valuable t
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Publications Radiation Data Radiati
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Rad Data Handbook 20.. - Voss Associates

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