Basic Info
Fission Yield
element
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Information about Molybdenum-101:
 |  |  | | | 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
| 1.48273E-03 |
5.08097E-02 |
| U-235 with 1.0 MeV
| 9.70035E-04 |
5.34959E-02 |
| U-238 with 1.0 MeV
| 1.90543E-04 |
6.08222E-02 |
| Pu-239 with 0.0253 eV
| 4.52314E-03 |
5.89526E-02 |
| Pu-239 with 1.0 MeV
| 5.06393E-03 |
6.53790E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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