Basic Info
Fission Yield
element
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Information about Silver-117:
 |  |  | | | 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
| 3.42223E-06 |
8.18213E-05 |
| U-235 with 1.0 MeV
| 1.17662E-05 |
2.43665E-04 |
| U-238 with 1.0 MeV
| 3.50335E-06 |
3.39042E-04 |
| Pu-239 with 0.0253 eV
| 3.70524E-05 |
2.70726E-04 |
| Pu-239 with 1.0 MeV
| 4.67473E-05 |
3.74222E-04 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 2.23920E-05 |
2.23920E-05 |
| U-235 with 1.0 MeV
| 8.83689E-05 |
8.83689E-05 |
| U-238 with 1.0 MeV
| 2.63116E-05 |
2.63116E-05 |
| Pu-239 with 0.0253 eV
| 2.42438E-04 |
2.42438E-04 |
| Pu-239 with 1.0 MeV
| 3.51093E-04 |
3.51093E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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