58-Ce-143
basic
fission yield
XS graphs
element
|
58-cerium-143
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 1.0 MeV
| .00000E+00 |
5.68865E-02 |
| U-238 with 1.0 MeV
| 1.37161E-06 |
4.56657E-02 |
| Pu-239 with 0.0253 eV
| 3.65458E-04 |
4.42858E-02 |
| Pu-239 with 1.0 MeV
| 2.80195E-04 |
4.29522E-02 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|