Basic Info
Fission Yield
element
|
Information about Silver-128:
 |  |  | | | 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
| 9.15796E-08 |
9.15990E-08 |
| U-235 with 1.0 MeV
| 3.40847E-07 |
3.40921E-07 |
| U-238 with 1.0 MeV
| 6.72788E-06 |
6.74019E-06 |
| Pu-239 with 0.0253 eV
| 1.36044E-08 |
1.36054E-08 |
| Pu-239 with 1.0 MeV
| 2.48075E-08 |
2.48091E-08 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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