Basic Info
Fission Yield
element
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Information about Tin-129:
 |  |  | | | 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 |
2.47925E-03 |
| U-235 with 1.0 MeV
| .00000E+00 |
5.12059E-04 |
| U-238 with 1.0 MeV
| 1.49784E-03 |
5.34812E-03 |
| Pu-239 with 0.0253 eV
| 2.58957E-03 |
3.24518E-03 |
| Pu-239 with 1.0 MeV
| 2.37223E-03 |
3.08486E-03 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
4.06253E-03 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.37742E-03 |
| U-238 with 1.0 MeV
| 4.19154E-03 |
4.67943E-03 |
| Pu-239 with 0.0253 eV
| 6.25300E-03 |
6.32818E-03 |
| Pu-239 with 1.0 MeV
| 6.63843E-03 |
6.72229E-03 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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