54-Xe-144
basic
fission yield
element
|
54-xenon-144
Fission Yields
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
6.25660E-05 |
U-235 with 1.0 MeV
| .00000E+00 |
1.12250E-04 |
U-238 with 1.0 MeV
| 1.27006E-03 |
1.27045E-03 |
Pu-239 with 0.0253 eV
| 6.26198E-06 |
6.26203E-06 |
Pu-239 with 1.0 MeV
| 7.50220E-06 |
7.50228E-06 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|