Basic Info
Fission Yield
element
|
Information about Molybdenum-93:
 |  |  | | | 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
| 3.47316E-16 |
5.59293E-16 |
| U-235 with 1.0 MeV
| 3.76274E-16 |
6.54441E-16 |
| U-238 with 1.0 MeV
| 1.01269E-18 |
1.76134E-18 |
| Pu-239 with 0.0253 eV
| 2.42154E-14 |
3.89948E-14 |
| Pu-239 with 1.0 MeV
| 1.04620E-14 |
1.81962E-14 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| 2.12232E-16 |
2.12232E-16 |
| U-235 with 1.0 MeV
| 2.78501E-16 |
2.78501E-16 |
| U-238 with 1.0 MeV
| 7.49545E-19 |
7.49545E-19 |
| Pu-239 with 0.0253 eV
| 1.47972E-14 |
1.47972E-14 |
| Pu-239 with 1.0 MeV
| 7.74348E-15 |
7.74348E-15 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|