Basic Info
Fission Yield
element
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Information about Molybdenum-109:
 |  |  | | | 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
| 3.80915E-06 |
3.81421E-06 |
| U-235 with 1.0 MeV
| 2.13304E-05 |
2.13763E-05 |
| U-238 with 1.0 MeV
| 2.79918E-04 |
2.81360E-04 |
| Pu-239 with 0.0253 eV
| 6.13499E-05 |
6.13945E-05 |
| Pu-239 with 1.0 MeV
| 7.31022E-05 |
7.31657E-05 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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