Basic Info
Fission Yield
element
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Information about Tin-130:
 |  |  | | | 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 |
4.08895E-03 |
| U-235 with 1.0 MeV
| .00000E+00 |
4.07634E-03 |
| U-238 with 1.0 MeV
| 3.86237E-03 |
6.91873E-03 |
| Pu-239 with 0.0253 eV
| 2.80821E-03 |
3.05709E-03 |
| Pu-239 with 1.0 MeV
| 2.53115E-03 |
2.80634E-03 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
7.38953E-03 |
| U-235 with 1.0 MeV
| .00000E+00 |
8.66367E-03 |
| U-238 with 1.0 MeV
| 1.05288E-02 |
1.05516E-02 |
| Pu-239 with 0.0253 eV
| 6.57703E-03 |
6.57767E-03 |
| Pu-239 with 1.0 MeV
| 6.89992E-03 |
6.90047E-03 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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