Basic Info
Fission Yield
element
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Information about Molybdenum-103:
 |  |  | | | 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
| 7.22658E-03 |
2.95326E-02 |
| U-235 with 1.0 MeV
| 7.55797E-03 |
3.26146E-02 |
| U-238 with 1.0 MeV
| 5.57842E-03 |
6.20701E-02 |
| Pu-239 with 0.0253 eV
| 3.18400E-02 |
6.80629E-02 |
| Pu-239 with 1.0 MeV
| 2.77626E-02 |
6.71630E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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