58-Ce-141
basic
fission yield
n-XS summary
XS graphs
element
|
58-cerium-141
Fission Yields
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 1.0 MeV
| .00000E+00 |
5.95364E-02 |
U-238 with 1.0 MeV
| 1.36160E-09 |
5.48315E-02 |
Pu-239 with 0.0253 eV
| 3.57116E-06 |
5.25758E-02 |
Pu-239 with 1.0 MeV
| 2.70082E-06 |
5.23815E-02 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|