Panasonic PT-DZ12000U

Spontaneous Fission Neutron and Gamma Yields
mrem / hr
SF (years) per Ci @ 30 cm
half-life n/s/Ci n/s/GBq neutron gamma
Es 6.7E5 7.14E3 1.92E2 0.1 0.1
253
Cf 85 2.64E9 7.14E7 2.93E4 1E4
252
Bk 6E8 1.25E2 3.38 <0.1 <0.1
249
Cm 1.38E7 1.11E5 3.0E3 1.2 0.4
244
Cm 7.2E6 5.28E3 1.43E2 <0.1 0.1
242
Am 2E14 0.18 4.86E-3 <0.1 <0.1
241
Pu 7E10 4.56E5 1.23E4 5.0 2.0
242
Pu 1.39E11 4.01E3 1.08E2 <0.1 0.1
240
Pu 5.5E15 0.37 1.0E-2 <0.1 <0.1
239
Pu 4.9E10 1.52E2 4.1 <0.1 <0.1
238
Pu 3.5E9 69.7 1.88 <0.1 <0.1
236
Np 1E18 0.18 4.86E-3 <0.1 <0.1
237
U 7E15 5.44E4 1.47E3 0.6 0.2
238
U 1.9E17 3.15E2 8.51 <0.1 <0.1
235
U 2E16 1.05 2.84E-2 <0.1 <0.1
234
U 8E 13 0. 07 1.89E-3 <0.1 <0 .1
232
Th 1E21 1.18 3.19E-2 <0.1 <0.1
232
These neutron and gamma exposure rates are approximate
values for the spontaneous fission process. When you are
making exposure rate measurements you should take into
account shielding of the source (including self-shielding),
individual instrument response to both neutron and gamma
radiation, isotopic mixtures, age of the material (for both decay
and ingrowth), homogeneity of the material, and impurities.
Refer to the Specific Activity and Characteristic Radiations of
Commonly Encountered Radionuclides sections for information
on gamma exposure rates and radiations from primary decay
modes of these isotopes.
167
Spontaneous Fission Neutron and Gamma Yields
mrem / hr
SF (years) per Ci @ 30 cm
half-life n/s/Ci n/s/GBq neutron gamma
Es 6.7E5 7.14E3 1.92E2 0.1 0.1
253
Cf 85 2.64E9 7.14E7 2.93E4 1E4
252
Bk 6E8 1.25E2 3.38 <0.1 <0.1
249
Cm 1.38E7 1.11E5 3.0E3 1.2 0.4
244
Cm 7.2E6 5.28E3 1.43E2 <0.1 0.1
242
Am 2E14 0.18 4.86E-3 <0.1 <0.1
241
Pu 7E10 4.56E5 1.23E4 5.0 2.0
242
Pu 1.39E11 4.01E3 1.08E2 <0.1 0.1
240
Pu 5.5E15 0.37 1.0E-2 <0.1 <0.1
239
Pu 4.9E10 1.52E2 4.1 <0.1 <0.1
238
Pu 3.5E9 69.7 1.88 <0.1 <0.1
236
Np 1E18 0.18 4.86E-3 <0.1 <0.1
237
U 7E15 5.44E4 1.47E3 0.6 0.2
238
U 1.9E17 3.15E2 8.51 <0.1 <0.1
235
U 2E16 1.05 2.84E-2 <0.1 <0.1
234
U 8E 13 0. 07 1.89E-3 <0.1 <0 .1
232
Th 1E21 1.18 3.19E-2 <0.1 <0.1
232
These neutron and gamma exposure rates are approximate
values for the spontaneous fission process. When you are
making exposure rate measurements you should take into
account shielding of the source (including self-shielding),
individual instrument response to both neutron and gamma
radiation, isotopic mixtures, age of the material (for both decay
and ingrowth), homogeneity of the material, and impurities.
Refer to the Specific Activity and Characteristic Radiations of
Commonly Encountered Radionuclides sections for information
on gamma exposure rates and radiations from primary decay
modes of these isotopes.
167
Spontaneous Fission Neutron and Gamma Yields
mrem / hr
SF (years) per Ci @ 30 cm
half-life n/s/Ci n/s/GBq neutron gamma
Es 6.7E5 7.14E3 1.92E2 0.1 0.1
253
Cf 85 2.64E9 7.14E7 2.93E4 1E4
252
Bk 6E8 1.25E2 3.38 <0.1 <0.1
249
Cm 1.38E7 1.11E5 3.0E3 1.2 0.4
244
Cm 7.2E6 5.28E3 1.43E2 <0.1 0.1
242
Am 2E14 0.18 4.86E-3 <0.1 <0.1
241
Pu 7E10 4.56E5 1.23E4 5.0 2.0
242
Pu 1.39E11 4.01E3 1.08E2 <0.1 0.1
240
Pu 5.5E15 0.37 1.0E-2 <0.1 <0.1
239
Pu 4.9E10 1.52E2 4.1 <0.1 <0.1
238
Pu 3.5E9 69.7 1.88 <0.1 <0.1
236
Np 1E18 0.18 4.86E-3 <0.1 <0.1
237
U 7E15 5.44E4 1.47E3 0.6 0.2
238
U 1.9E17 3.15E2 8.51 <0.1 <0.1
235
U 2E16 1.05 2.84E-2 <0.1 <0.1
234
U 8E 13 0. 07 1.89E-3 <0.1 <0 .1
232
Th 1E21 1.18 3.19E-2 <0.1 <0.1
232
These neutron and gamma exposure rates are approximate
values for the spontaneous fission process. When you are
making exposure rate measurements you should take into
account shielding of the source (including self-shielding),
individual instrument response to both neutron and gamma
radiation, isotopic mixtures, age of the material (for both decay
and ingrowth), homogeneity of the material, and impurities.
Refer to the Specific Activity and Characteristic Radiations of
Commonly Encountered Radionuclides sections for information
on gamma exposure rates and radiations from primary decay
modes of these isotopes.
167
Spontaneous Fission Neutron and Gamma Yields
mrem / hr
SF (years) per Ci @ 30 cm
half-life n/s/Ci n/s/GBq neutron gamma
Es 6.7E5 7.14E3 1.92E2 0.1 0.1
253
Cf 85 2.64E9 7.14E7 2.93E4 1E4
252
Bk 6E8 1.25E2 3.38 <0.1 <0.1
249
Cm 1.38E7 1.11E5 3.0E3 1.2 0.4
244
Cm 7.2E6 5.28E3 1.43E2 <0.1 0.1
242
Am 2E14 0.18 4.86E-3 <0.1 <0.1
241
Pu 7E10 4.56E5 1.23E4 5.0 2.0
242
Pu 1.39E11 4.01E3 1.08E2 <0.1 0.1
240
Pu 5.5E15 0.37 1.0E-2 <0.1 <0.1
239
Pu 4.9E10 1.52E2 4.1 <0.1 <0.1
238
Pu 3.5E9 69.7 1.88 <0.1 <0.1
236
Np 1E18 0.18 4.86E-3 <0.1 <0.1
237
U 7E15 5.44E4 1.47E3 0.6 0.2
238
U 1.9E17 3.15E2 8.51 <0.1 <0.1
235
U 2E16 1.05 2.84E-2 <0.1 <0.1
234
U 8E 13 0. 07 1.89E-3 <0.1 <0 .1
232
Th 1E21 1.18 3.19E-2 <0.1 <0.1
232
These neutron and gamma exposure rates are approximate
values for the spontaneous fission process. When you are
making exposure rate measurements you should take into
account shielding of the source (including self-shielding),
individual instrument response to both neutron and gamma
radiation, isotopic mixtures, age of the material (for both decay
and ingrowth), homogeneity of the material, and impurities.
Refer to the Specific Activity and Characteristic Radiations of
Commonly Encountered Radionuclides sections for information
on gamma exposure rates and radiations from primary decay
modes of these isotopes.
167