Basic Info
Fission Yield
element
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Information about Silver-105:
 |  |  | | | 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
| 2.49872E-20 |
1.87925E-19 |
| U-235 with 1.0 MeV
| 4.33935E-20 |
3.68189E-19 |
| U-238 with 1.0 MeV
| 2.06610E-22 |
1.75306E-21 |
| Pu-239 with 0.0253 eV
| 2.23100E-17 |
1.67790E-16 |
| Pu-239 with 1.0 MeV
| 1.32192E-17 |
1.12164E-16 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 1.63494E-19 |
1.63494E-19 |
| U-235 with 1.0 MeV
| 3.25904E-19 |
3.25904E-19 |
| U-238 with 1.0 MeV
| 1.55173E-21 |
1.55173E-21 |
| Pu-239 with 0.0253 eV
| 1.45976E-16 |
1.45976E-16 |
| Pu-239 with 1.0 MeV
| 9.92820E-17 |
9.92820E-17 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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