Basic Info
Fission Yield
n-XS summary
element
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Information about Antimony-124:
 |  |  |  | Wikipedia | Neutron Cross Sections | X-Ray Transitions | X-Ray Attenuation |
Fission Yields
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
1.06136E-07 |
U-235 with 1.0 MeV
| .00000E+00 |
4.22059E-08 |
U-238 with 1.0 MeV
| 1.28495E-10 |
4.55001E-10 |
Pu-239 with 0.0253 eV
| 2.22247E-07 |
7.02261E-07 |
Pu-239 with 1.0 MeV
| 3.08984E-07 |
1.09411E-06 |
Fission Yields to Meta State
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
9.06831E-08 |
U-235 with 1.0 MeV
| .00000E+00 |
3.78584E-08 |
U-238 with 1.0 MeV
| 2.69601E-10 |
4.08133E-10 |
Pu-239 with 0.0253 eV
| 3.99787E-07 |
6.00018E-07 |
Pu-239 with 1.0 MeV
| 6.48291E-07 |
9.81407E-07 |
U-235 with 0.0253 eV
| .00000E+00 |
3.02617E-08 |
U-235 with 1.0 MeV
| .00000E+00 |
1.28502E-08 |
U-238 with 1.0 MeV
| 1.38532E-10 |
1.38532E-10 |
Pu-239 with 0.0253 eV
| 2.00231E-07 |
2.00231E-07 |
Pu-239 with 1.0 MeV
| 3.33117E-07 |
3.33117E-07 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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