Basic Info
Fission Yield
element
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Information about Xenon-143:
 |  |  | | | 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 |
1.55485E-04 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.67109E-04 |
| U-238 with 1.0 MeV
| 1.07145E-03 |
1.08061E-03 |
| Pu-239 with 0.0253 eV
| 2.70961E-05 |
2.71013E-05 |
| Pu-239 with 1.0 MeV
| 2.62986E-05 |
2.63063E-05 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
3.75147E-04 |
| U-235 with 1.0 MeV
| .00000E+00 |
4.66826E-04 |
| U-238 with 1.0 MeV
| 2.99835E-03 |
2.99835E-03 |
| Pu-239 with 0.0253 eV
| 6.54286E-05 |
6.54286E-05 |
| Pu-239 with 1.0 MeV
| 7.35939E-05 |
7.35939E-05 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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