Basic Info
Fission Yield
element
|
Information about Silver-122:
 |  |  | | | 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
| 2.09653E-05 |
2.17987E-05 |
| U-235 with 1.0 MeV
| 7.68156E-05 |
7.99576E-05 |
| U-238 with 1.0 MeV
| 1.21673E-04 |
1.50698E-04 |
| Pu-239 with 0.0253 eV
| 3.33108E-05 |
3.37971E-05 |
| Pu-239 with 1.0 MeV
| 5.49567E-05 |
5.56772E-05 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|