Basic Info
Fission Yield
element
|
Information about Samarium-146:
 |  |  | | | 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 |
9.54174E-13 |
| U-238 with 1.0 MeV
| 2.11184E-21 |
9.73512E-16 |
| Pu-239 with 0.0253 eV
| 1.95274E-15 |
7.51356E-11 |
| Pu-239 with 1.0 MeV
| 1.18859E-15 |
5.10763E-11 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|