Basic Info
Fission Yield
element
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Information about Silver-108:
 |  |  | | | 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
| 1.83677E-12 |
2.21963E-12 |
| U-235 with 1.0 MeV
| 1.36813E-12 |
1.70006E-12 |
| U-238 with 1.0 MeV
| 4.24542E-14 |
5.27542E-14 |
| Pu-239 with 0.0253 eV
| 5.59716E-10 |
6.76385E-10 |
| Pu-239 with 1.0 MeV
| 3.16790E-10 |
3.93648E-10 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 4.30184E-12 |
4.30184E-12 |
| U-235 with 1.0 MeV
| 3.72953E-12 |
3.72953E-12 |
| U-238 with 1.0 MeV
| 1.15730E-13 |
1.15730E-13 |
| Pu-239 with 0.0253 eV
| 1.31089E-09 |
1.31089E-09 |
| Pu-239 with 1.0 MeV
| 8.63569E-10 |
8.63569E-10 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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