Basic Info
Fission Yield
element
|
Information about Cerium-156:
 |  |  | | | 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 |
2.36894E-09 |
| U-238 with 1.0 MeV
| 3.34389E-07 |
3.34392E-07 |
| Pu-239 with 0.0253 eV
| 3.48108E-10 |
3.48113E-10 |
| Pu-239 with 1.0 MeV
| 6.12176E-10 |
6.12185E-10 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|