Basic Info
Fission Yield
element
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Information about Silver-115:
 |  |  | | | 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
| 9.56953E-07 |
7.69823E-05 |
| U-235 with 1.0 MeV
| 1.77350E-06 |
2.12269E-04 |
| U-238 with 1.0 MeV
| 2.68221E-07 |
2.53867E-04 |
| Pu-239 with 0.0253 eV
| 7.77650E-06 |
2.33066E-04 |
| Pu-239 with 1.0 MeV
| 1.37755E-05 |
4.66555E-04 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 6.26144E-06 |
3.43804E-05 |
| U-235 with 1.0 MeV
| 1.33197E-05 |
9.11742E-05 |
| U-238 with 1.0 MeV
| 2.01446E-06 |
9.58114E-05 |
| Pu-239 with 0.0253 eV
| 5.08824E-05 |
1.34209E-04 |
| Pu-239 with 1.0 MeV
| 1.03460E-04 |
2.70926E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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