Basic Info
Fission Yield
element
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Information about Tin-127:
 |  |  | | | 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 |
4.78032E-04 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.02510E-03 |
| U-238 with 1.0 MeV
| 1.21924E-04 |
2.72578E-04 |
| Pu-239 with 0.0253 eV
| 2.06967E-03 |
2.26212E-03 |
| Pu-239 with 1.0 MeV
| 2.44778E-03 |
2.66963E-03 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
7.09376E-04 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.72435E-03 |
| U-238 with 1.0 MeV
| 4.35692E-05 |
9.86986E-04 |
| Pu-239 with 0.0253 eV
| 8.57118E-04 |
2.32058E-03 |
| Pu-239 with 1.0 MeV
| 8.74707E-04 |
2.49513E-03 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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