Basic Info
Fission Yield
element
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Information about Silver-114:
 |  |  | | | 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
| 2.26949E-06 |
1.40350E-04 |
| U-235 with 1.0 MeV
| 3.86827E-06 |
3.29110E-04 |
| U-238 with 1.0 MeV
| 3.31388E-07 |
3.93597E-04 |
| Pu-239 with 0.0253 eV
| 3.21304E-05 |
6.05822E-04 |
| Pu-239 with 1.0 MeV
| 4.93660E-05 |
9.30966E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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