Basic Info
Fission Yield
element
|
Information about Cerium-143:
 |  |  | | | 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 |
5.68865E-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)
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