58-Ce-146
basic
fission yield
element
|
58-cerium-146
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 1.0 MeV
| .00000E+00 |
2.89638E-02 |
| U-238 with 1.0 MeV
| 1.32199E-03 |
3.39505E-02 |
| Pu-239 with 0.0253 eV
| 1.15418E-02 |
2.42020E-02 |
| Pu-239 with 1.0 MeV
| 1.01274E-02 |
2.39951E-02 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|