Basic Info
Fission Yield
element
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Information about Silver-106:
 |  |  | | | 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
| 7.93326E-18 |
7.93326E-18 |
| U-235 with 1.0 MeV
| 1.63475E-17 |
1.63475E-17 |
| U-238 with 1.0 MeV
| 1.41502E-19 |
1.41502E-19 |
| Pu-239 with 0.0253 eV
| 1.20922E-14 |
1.20922E-14 |
| Pu-239 with 1.0 MeV
| 4.02700E-15 |
4.02700E-15 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 1.85802E-17 |
1.85802E-17 |
| U-235 with 1.0 MeV
| 4.45631E-17 |
4.45631E-17 |
| U-238 with 1.0 MeV
| 3.85734E-19 |
3.85734E-19 |
| Pu-239 with 0.0253 eV
| 2.83208E-14 |
2.83208E-14 |
| Pu-239 with 1.0 MeV
| 1.09776E-14 |
1.09776E-14 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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