Basic Info
Fission Yield
element
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Information about Molybdenum-106:
 |  |  | | | 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
| 3.55460E-03 |
3.69972E-03 |
| U-235 with 1.0 MeV
| 3.76076E-03 |
4.18152E-03 |
| U-238 with 1.0 MeV
| 1.96832E-02 |
2.35551E-02 |
| Pu-239 with 0.0253 eV
| 1.94604E-02 |
2.03024E-02 |
| Pu-239 with 1.0 MeV
| 2.27570E-02 |
2.40276E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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