Basic Info
Fission Yield
element
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Information about Tin-121:
 |  |  | | | 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 |
1.28041E-04 |
| U-235 with 1.0 MeV
| .00000E+00 |
3.47154E-04 |
| U-238 with 1.0 MeV
| 1.39696E-09 |
4.30557E-04 |
| Pu-239 with 0.0253 eV
| 3.64427E-07 |
3.76795E-04 |
| Pu-239 with 1.0 MeV
| 5.33546E-07 |
6.73465E-04 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
7.10713E-06 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.75597E-05 |
| U-238 with 1.0 MeV
| 3.90926E-09 |
1.16804E-05 |
| Pu-239 with 0.0253 eV
| 8.79976E-07 |
2.62338E-05 |
| Pu-239 with 1.0 MeV
| 1.49307E-06 |
4.77587E-05 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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