Basic Info
Fission Yield
element
|
Information about Silver-121:
 |  |  | | | 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
| 3.81815E-05 |
4.10668E-05 |
| U-235 with 1.0 MeV
| 1.29522E-04 |
1.40521E-04 |
| U-238 with 1.0 MeV
| 2.11888E-04 |
2.95074E-04 |
| Pu-239 with 0.0253 eV
| 6.40007E-05 |
6.59131E-05 |
| Pu-239 with 1.0 MeV
| 1.24478E-04 |
1.28053E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|