54-Xe-147
basic
fission yield
element
|
54-xenon-147
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
5.24134E-11 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.82110E-10 |
| U-238 with 1.0 MeV
| 4.90934E-08 |
4.90938E-08 |
| Pu-239 with 0.0253 eV
| 1.17108E-12 |
1.17120E-12 |
| Pu-239 with 1.0 MeV
| 1.87494E-12 |
1.87513E-12 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|