Rad Data Handbook 20.. - Voss Associates

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Isotopic Mix of 20% Enriched U 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 79.68 - - - - - - 20.0 - - - 0.32 % Activity 1.25 1.25 1.25 2.00 2.00 92.25 Curies for a 1 kilo-gram mixture of 20% enriched uranium 2.7E-4 2.7E-4 2.7E-4 4.3E-4 4.3E-4 2.0E-2 gamma exposure rates in rem/hr at 30 cm 1.1E-7 9.6E-6 1.4E-5 3.2E-4 2.1E-5 6.0E-6 Total gamma exposure rate 3.7E-4 Rem/hr at 30 cm Isotopic Mix of Depleted U 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 99.75 - - - - - - 0.25 - - - 0.0005 % Activity 32.01 32.01 32.01 0.53 0.53 2.90 Curies for a 1 kilo-gram mixture of depleted uranium 3.4E-4 3.4E-4 3.4E-4 5.4E-6 5.4E-6 3.1E-5 gamma exposure rates in rem/hr at 30 cm 1.4E-7 1.2E-5 1.7E-5 4.1E-6 2.6E-7 9.3E-9 Total gamma exposure rate 3.3E-5 Rem/hr at 30 cm Isotopic Mix of HEU 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 6.7 - - - - - - 93.2 - - - 0.01 % Activity 0.5 0.5 0.5 42.6 42.6 13.3 Curies for a 1 kilo-gram mixture of HEU 2.3E-5 2.3E-5 2.3E-5 2.0E-3 2.0E-3 6.2E-4 gamma exposure rates in rem/hr at 30 cm 9.2E-9 8.2E-7 1.2E-6 1.5E-3 9.6E-5 1.9E-7 Total gamma exposure rate 1.6E-3 Rem/hr at 30 cm Isotopic Mix of 20% Enriched U 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 79.68 - - - - - - 20.0 - - - 0.32 % Activity 1.25 1.25 1.25 2.00 2.00 92.25 Curies for a 1 kilo-gram mixture of 20% enriched uranium 2.7E-4 2.7E-4 2.7E-4 4.3E-4 4.3E-4 2.0E-2 gamma exposure rates in rem/hr at 30 cm 1.1E-7 9.6E-6 1.4E-5 3.2E-4 2.1E-5 6.0E-6 Total gamma exposure rate 3.7E-4 Rem/hr at 30 cm Isotopic Mix of Depleted U 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 99.75 - - - - - - 0.25 - - - 0.0005 % Activity 32.01 32.01 32.01 0.53 0.53 2.90 Curies for a 1 kilo-gram mixture of depleted uranium 3.4E-4 3.4E-4 3.4E-4 5.4E-6 5.4E-6 3.1E-5 gamma exposure rates in rem/hr at 30 cm 1.4E-7 1.2E-5 1.7E-5 4.1E-6 2.6E-7 9.3E-9 Total gamma exposure rate 3.3E-5 Rem/hr at 30 cm Isotopic Mix of HEU 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 6.7 - - - - - - 93.2 - - - 0.01 % Activity 0.5 0.5 0.5 42.6 42.6 13.3 Curies for a 1 kilo-gram mixture of HEU 2.3E-5 2.3E-5 2.3E-5 2.0E-3 2.0E-3 6.2E-4 gamma exposure rates in rem/hr at 30 cm 9.2E-9 8.2E-7 1.2E-6 1.5E-3 9.6E-5 1.9E-7 Total gamma exposure rate 1.6E-3 Rem/hr at 30 cm 138 138 Isotopic Mix of 20% Enriched U 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 79.68 - - - - - - 20.0 - - - 0.32 % Activity 1.25 1.25 1.25 2.00 2.00 92.25 Curies for a 1 kilo-gram mixture of 20% enriched uranium 2.7E-4 2.7E-4 2.7E-4 4.3E-4 4.3E-4 2.0E-2 gamma exposure rates in rem/hr at 30 cm 1.1E-7 9.6E-6 1.4E-5 3.2E-4 2.1E-5 6.0E-6 Total gamma exposure rate 3.7E-4 Rem/hr at 30 cm Isotopic Mix of Depleted U 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 99.75 - - - - - - 0.25 - - - 0.0005 % Activity 32.01 32.01 32.01 0.53 0.53 2.90 Curies for a 1 kilo-gram mixture of depleted uranium 3.4E-4 3.4E-4 3.4E-4 5.4E-6 5.4E-6 3.1E-5 gamma exposure rates in rem/hr at 30 cm 1.4E-7 1.2E-5 1.7E-5 4.1E-6 2.6E-7 9.3E-9 Total gamma exposure rate 3.3E-5 Rem/hr at 30 cm Isotopic Mix of HEU 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 6.7 - - - - - - 93.2 - - - 0.01 % Activity 0.5 0.5 0.5 42.6 42.6 13.3 Curies for a 1 kilo-gram mixture of HEU 2.3E-5 2.3E-5 2.3E-5 2.0E-3 2.0E-3 6.2E-4 gamma exposure rates in rem/hr at 30 cm 9.2E-9 8.2E-7 1.2E-6 1.5E-3 9.6E-5 1.9E-7 Total gamma exposure rate 1.6E-3 Rem/hr at 30 cm Isotopic Mix of 20% Enriched U 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 79.68 - - - - - - 20.0 - - - 0.32 % Activity 1.25 1.25 1.25 2.00 2.00 92.25 Curies for a 1 kilo-gram mixture of 20% enriched uranium 2.7E-4 2.7E-4 2.7E-4 4.3E-4 4.3E-4 2.0E-2 gamma exposure rates in rem/hr at 30 cm 1.1E-7 9.6E-6 1.4E-5 3.2E-4 2.1E-5 6.0E-6 Total gamma exposure rate 3.7E-4 Rem/hr at 30 cm Isotopic Mix of Depleted U 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 99.75 - - - - - - 0.25 - - - 0.0005 % Activity 32.01 32.01 32.01 0.53 0.53 2.90 Curies for a 1 kilo-gram mixture of depleted uranium 3.4E-4 3.4E-4 3.4E-4 5.4E-6 5.4E-6 3.1E-5 gamma exposure rates in rem/hr at 30 cm 1.4E-7 1.2E-5 1.7E-5 4.1E-6 2.6E-7 9.3E-9 Total gamma exposure rate 3.3E-5 Rem/hr at 30 cm Isotopic Mix of HEU 238 U 234 Th 234m Pa 235 U 231 Th 234 U % Weight 6.7 - - - - - - 93.2 - - - 0.01 % Activity 0.5 0.5 0.5 42.6 42.6 13.3 Curies for a 1 kilo-gram mixture of HEU 2.3E-5 2.3E-5 2.3E-5 2.0E-3 2.0E-3 6.2E-4 gamma exposure rates in rem/hr at 30 cm 9.2E-9 8.2E-7 1.2E-6 1.5E-3 9.6E-5 1.9E-7 Total gamma exposure rate 1.6E-3 Rem/hr at 30 cm 138 138
MISCELLANEOUS RULES OF THUMB 1. One watt of power in a reactor requires 3.1E10 fissions per second. In a reactor operating for more than 4 days, the total fission products are about 3 Ci / watt at 1.5 min after shutdown. At 2 yr after shutdown, the fission products are approximately 75 Ci / MW-day. 2. The quantity of a short-lived fission product in a reactor which has been operated about four times as long as the half-life is given by; Ci (FY)(PL) , where FY is the fission yield (%/100) and PL is the power level in watts. 3. Correction factor for unsealed ion chambers to STP (0 0 C and 760 mm of Hg) is f = (t + 273)/(273) x (760 / P) where t is the ambient temperature in degrees C and P is the ambient barometric pressure in mm of Hg. 4. The activity of an isotope (without radioactive daughter) is reduced to less than 1% after seven half-lives. 5. NATURALLY OCCURRING RADIONUCLIDES Primordial Cosmogonic 40 K Tritium 87 7 Rb Be Natural U and Th C 14 6. Unified Time, Distance, and Shielding formula for reduction of external dose. 2 n Rem = Initial Rem/hr x T in hours x (D 2) x 0.5 2 (D) 1 Where: Rem is the dose after applying reduction methods T is the exposure time in hours D 1 is the initial distance to the source D 2 is the new distance to the source n 0.5 is the Shielding for ‘n’ half-value layers MISCELLANEOUS RULES OF THUMB 1. One watt of power in a reactor requires 3.1E10 fissions per second. In a reactor operating for more than 4 days, the total fission products are about 3 Ci / watt at 1.5 min after shutdown. At 2 yr after shutdown, the fission products are approximately 75 Ci / MW-day. 2. The quantity of a short-lived fission product in a reactor which has been operated about four times as long as the half-life is given by; Ci (FY)(PL) , where FY is the fission yield (%/100) and PL is the power level in watts. 3. Correction factor for unsealed ion chambers to STP (0 0 C and 760 mm of Hg) is f = (t + 273)/(273) x (760 / P) where t is the ambient temperature in degrees C and P is the ambient barometric pressure in mm of Hg. 4. The activity of an isotope (without radioactive daughter) is reduced to less than 1% after seven half-lives. 5. NATURALLY OCCURRING RADIONUCLIDES Primordial Cosmogonic 40 K Tritium 87 7 Rb Be Natural U and Th C 14 6. Unified Time, Distance, and Shielding formula for reduction of external dose. 2 n Rem = Initial Rem/hr x T in hours x (D 2) x 0.5 2 (D) 1 Where: Rem is the dose after applying reduction methods T is the exposure time in hours D 1 is the initial distance to the source D 2 is the new distance to the source n 0.5 is the Shielding for ‘n’ half-value layers MISCELLANEOUS RULES OF THUMB 1. One watt of power in a reactor requires 3.1E10 fissions per second. In a reactor operating for more than 4 days, the total fission products are about 3 Ci / watt at 1.5 min after shutdown. At 2 yr after shutdown, the fission products are approximately 75 Ci / MW-day. 2. The quantity of a short-lived fission product in a reactor which has been operated about four times as long as the half-life is given by; Ci (FY)(PL) , where FY is the fission yield (%/100) and PL is the power level in watts. 3. Correction factor for unsealed ion chambers to STP (0 0 C and 760 mm of Hg) is f = (t + 273)/(273) x (760 / P) where t is the ambient temperature in degrees C and P is the ambient barometric pressure in mm of Hg. 4. The activity of an isotope (without radioactive daughter) is reduced to less than 1% after seven half-lives. 5. NATURALLY OCCURRING RADIONUCLIDES Primordial Cosmogonic 40 K Tritium 87 7 Rb Be Natural U and Th C 14 6. Unified Time, Distance, and Shielding formula for reduction of external dose. 2 n Rem = Initial Rem/hr x T in hours x (D 2) x 0.5 2 (D) 1 Where: Rem is the dose after applying reduction methods T is the exposure time in hours D 1 is the initial distance to the source D 2 is the new distance to the source n 0.5 is the Shielding for ‘n’ half-value layers MISCELLANEOUS RULES OF THUMB 1. One watt of power in a reactor requires 3.1E10 fissions per second. In a reactor operating for more than 4 days, the total fission products are about 3 Ci / watt at 1.5 min after shutdown. At 2 yr after shutdown, the fission products are approximately 75 Ci / MW-day. 2. The quantity of a short-lived fission product in a reactor which has been operated about four times as long as the half-life is given by; Ci (FY)(PL) , where FY is the fission yield (%/100) and PL is the power level in watts. 3. Correction factor for unsealed ion chambers to STP (0 0 C and 760 mm of Hg) is f = (t + 273)/(273) x (760 / P) where t is the ambient temperature in degrees C and P is the ambient barometric pressure in mm of Hg. 4. The activity of an isotope (without radioactive daughter) is reduced to less than 1% after seven half-lives. 5. NATURALLY OCCURRING RADIONUCLIDES Primordial Cosmogonic 40 K Tritium 87 7 Rb Be Natural U and Th C 14 6. Unified Time, Distance, and Shielding formula for reduction of external dose. 2 n Rem = Initial Rem/hr x T in hours x (D 2) x 0.5 2 (D) 1 Where: Rem is the dose after applying reduction methods T is the exposure time in hours D 1 is the initial distance to the source D 2 is the new distance to the source n 0.5 is the Shielding for ‘n’ half-value layers
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Abbreviations 115 Activity vs Expos
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RADIOLOGICAL EMERGENCY RESPONSE Wri
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HAZARD CONTROL PRIORITIES DURING ME
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ACUTE RADIATION EFFECTS 0 - 25 REM
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TABLE OF THE ELEMENTS Z Density Z D
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Relative Locations of Products of N
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RADIOACTIVE DECAY MODES OF COMMONLY
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Progeny kev and % abundance 55 Fe 5
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Progeny kev and % abundance 99 Mo 9
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Progeny kev and % abundance 208 Tl
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Progeny kev and % abundance 229 Th
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Progeny kev and % abundance 241 Am
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Progeny kev and % abundance Progeny
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Progeny kev and % abundance 222 Rn
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Neptunium Decay Chain (4n + 1) st 1
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Actinium Decay Chain (4n + 3) st 1
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Ci / g = 3.578E5 / (T 1/2 in years
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Rem/hr / Ci Sv/hr / GBq Half-Life C
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mRem/hr mSv/hr 1ì 10ì 100ì 1ì 1
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RADIATION BIOLOGY Maximum survivabl
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INTERNAL DOSIMETRY Calculating CDE
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EQUIVALENT DOSE, EFFECTIVE DOSE, an
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CALCULATING TODE AND TEDE TEDE = DD
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SHIELDING MATERIALS α a single she
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Beta Dose Rates in rad/hr per mCi M
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Combining Radiation Types to Determ
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NEUTRON SHIELD THICKNESS I = I0e -N
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Exposure Rate in an Air-Filled Ion
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Inverse Square Law 2 2 X 1 (D) 1 =
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Table 1 of DOE 5400.5 Surface Activ
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6CEN The 6CEN equation can be used
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Ventilation Rates Ventilation rates
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AIR FLOW METER CORRECTIONS Mass Flo
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10CFR20 DAC 10CFR835 DAC 10CFR20 AL
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Page 89 and 90: 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
Page 117 and 118: ABBREVIATIONS ampere A, or amp angs
Page 119 and 120: Mass 1 gram = 0.03527 ounces 1 ounc
Page 121 and 122: Radiological 1 BTU = 235 1.28E-8 g
Page 123 and 124: CONSTANTS Avogadro's number (N 0) 6
Page 125 and 126: ELECTROMAGNETIC SPECTRUM Wavelength
Page 127 and 128: 5. Air-proportional alpha detectors
Page 129 and 130: 32 7. The bremsstrahlung from a 1 C
Page 131 and 132: RULES OF THUMB FOR NEUTRONS 1. The
Page 133 and 134: Spontaneous Fission Neutron and Gam
Page 135 and 136: Energy & Yield of neutrons from the
Page 137 and 138: WG Pu 15 years after fabrication 23
Page 139: Isotopic Mix of Natural U 238 U 234
Page 143 and 144: PUBLIC RADIATION DOSES Average per
Page 145 and 146: COMPARATIVE RISKS OF RADIATION EXPO
Page 147 and 148: Voss Associates provides valuable t
Page 149: Publications Radiation Data Radiati
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