Basic Info
Fission Yield
n-XS summary
element
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Information about Molybdenum-100:
 |  |  | | | 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
| 5.79601E-04 |
6.23231E-02 |
| U-235 with 1.0 MeV
| 1.88426E-04 |
6.32861E-02 |
| U-238 with 1.0 MeV
| 2.57402E-05 |
6.69985E-02 |
| Pu-239 with 0.0253 eV
| 1.21474E-03 |
6.82630E-02 |
| Pu-239 with 1.0 MeV
| 8.38884E-04 |
6.57116E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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