Basic Info
Fission Yield
element
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Information about Manganese-67:
 |  |  | | | 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
| 2.54943E-11 |
2.55558E-11 |
| U-235 with 1.0 MeV
| 3.41847E-10 |
3.42887E-10 |
| U-238 with 1.0 MeV
| 2.67313E-11 |
2.70647E-11 |
| Pu-239 with 0.0253 eV
| 7.86150E-12 |
7.86255E-12 |
| Pu-239 with 1.0 MeV
| 8.58260E-11 |
8.59310E-11 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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