Basic Info
Fission Yield
n-XS summary
element
|
Information about Tin-114:
 |  |  | | | 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
| .00000E+00 |
1.11996E-12 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.04540E-12 |
| U-238 with 1.0 MeV
| 1.11888E-20 |
4.06786E-15 |
| Pu-239 with 0.0253 eV
| 2.48013E-15 |
9.66545E-11 |
| Pu-239 with 1.0 MeV
| 3.12409E-15 |
1.30571E-10 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|