Basic Info
Fission Yield
element
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Information about Molybdenum-108:
 |  |  | | | 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
| 5.07587E-05 |
5.09577E-05 |
| U-235 with 1.0 MeV
| 1.81489E-04 |
1.82709E-04 |
| U-238 with 1.0 MeV
| 2.33424E-03 |
2.36490E-03 |
| Pu-239 with 0.0253 eV
| 6.33425E-04 |
6.34926E-04 |
| Pu-239 with 1.0 MeV
| 6.40414E-04 |
6.42344E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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