Basic Info
Fission Yield
n-XS summary
element
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Information about Molybdenum-97:
 |  |  | | | 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
| 1.62964E-07 |
6.00817E-02 |
| U-235 with 1.0 MeV
| 4.92779E-08 |
5.99052E-02 |
| U-238 with 1.0 MeV
| 1.47171E-09 |
5.57464E-02 |
| Pu-239 with 0.0253 eV
| 8.45274E-07 |
5.44524E-02 |
| Pu-239 with 1.0 MeV
| 4.86147E-07 |
5.32403E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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