Basic Info
Fission Yield
element
|
Information about Xenon-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 |
2.22260E-17 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.34185E-16 |
| U-238 with 1.0 MeV
| 3.31634E-21 |
1.97910E-20 |
| Pu-239 with 0.0253 eV
| 4.79068E-15 |
2.55083E-14 |
| Pu-239 with 1.0 MeV
| 4.87769E-15 |
2.91088E-14 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
1.80518E-17 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.11700E-16 |
| U-238 with 1.0 MeV
| 1.64747E-20 |
1.64747E-20 |
| Pu-239 with 0.0253 eV
| 2.07176E-14 |
2.07176E-14 |
| Pu-239 with 1.0 MeV
| 2.42311E-14 |
2.42311E-14 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
|