Basic Info
Fission Yield
element
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Information about Molybdenum-107:
 |  |  | | | 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
| 1.01163E-03 |
1.03029E-03 |
| U-235 with 1.0 MeV
| 1.37848E-03 |
1.42945E-03 |
| U-238 with 1.0 MeV
| 9.03129E-03 |
9.70929E-03 |
| Pu-239 with 0.0253 eV
| 7.24965E-03 |
7.35064E-03 |
| Pu-239 with 1.0 MeV
| 7.00395E-03 |
7.12287E-03 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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