Basic Info
Fission Yield
element
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Information about Silver-126:
 |  |  | | | 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
| 1.09975E-06 |
1.10144E-06 |
| U-235 with 1.0 MeV
| 4.41802E-06 |
4.42495E-06 |
| U-238 with 1.0 MeV
| 1.51678E-05 |
1.53450E-05 |
| Pu-239 with 0.0253 eV
| 9.24299E-07 |
9.24792E-07 |
| Pu-239 with 1.0 MeV
| 1.09033E-06 |
1.09084E-06 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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