Basic Info
Fission Yield
n-XS summary
element
|
Information about Cerium-144:
 |  |  | | | 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 |
5.25801E-02 |
| U-238 with 1.0 MeV
| 2.26165E-05 |
4.53722E-02 |
| Pu-239 with 0.0253 eV
| 1.93371E-03 |
3.73679E-02 |
| Pu-239 with 1.0 MeV
| 1.49561E-03 |
3.62062E-02 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|