51-Sb-127
basic
fission yield
XS graphs
element
|
51-antimony-127
Fission Yields
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
1.24644E-03 |
U-235 with 1.0 MeV
| .00000E+00 |
2.79095E-03 |
U-238 with 1.0 MeV
| 1.03121E-06 |
1.26060E-03 |
Pu-239 with 0.0253 eV
| 3.09460E-04 |
4.89216E-03 |
Pu-239 with 1.0 MeV
| 3.58729E-04 |
5.52349E-03 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|