Basic Info
Fission Yield
element
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Information about Silver-127:
 |  |  | | | 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
| 3.99897E-07 |
3.99911E-07 |
| U-235 with 1.0 MeV
| 1.53924E-06 |
1.53931E-06 |
| U-238 with 1.0 MeV
| 1.08964E-05 |
1.09028E-05 |
| Pu-239 with 0.0253 eV
| 2.16068E-07 |
2.16069E-07 |
| Pu-239 with 1.0 MeV
| 2.32068E-07 |
2.32069E-07 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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