Basic Info
Fission Yield
element
|
Information about Manganese-66:
 |  |  | | | Wikipedia | Neutron Cross Sections | X-Ray Transitions | X-Ray Attenuation |
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 2.28949E-11 |
2.31059E-11 |
| U-235 with 1.0 MeV
| 4.54796E-10 |
4.59684E-10 |
| U-238 with 1.0 MeV
| 1.89222E-11 |
1.98773E-11 |
| Pu-239 with 0.0253 eV
| 2.53082E-11 |
2.54132E-11 |
| Pu-239 with 1.0 MeV
| 1.61049E-10 |
1.61744E-10 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|