51-Sb-119
basic
fission yield
XS graphs
element
|
51-antimony-119
Fission Yields
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
3.64919E-14 |
U-235 with 1.0 MeV
| .00000E+00 |
3.87826E-14 |
U-238 with 1.0 MeV
| 7.53296E-17 |
7.53296E-17 |
Pu-239 with 0.0253 eV
| 3.13098E-12 |
3.13100E-12 |
Pu-239 with 1.0 MeV
| 4.61136E-12 |
4.61140E-12 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|