Basic Info
Fission Yield
element
|
Information about Cerium-154:
 |  |  | | | Wikipedia | Neutron Cross Sections | X-Ray Transitions | X-Ray Attenuation |
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 1.0 MeV
| .00000E+00 |
9.59954E-07 |
| U-238 with 1.0 MeV
| 4.48225E-05 |
4.48747E-05 |
| Pu-239 with 0.0253 eV
| 2.38077E-07 |
2.38102E-07 |
| Pu-239 with 1.0 MeV
| 3.09094E-07 |
3.09136E-07 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|