51-Sb-121
basic
fission yield
n-XS summary
XS graphs
element
|
51-antimony-121
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
1.29633E-04 |
| U-235 with 1.0 MeV
| .00000E+00 |
3.51087E-04 |
| U-238 with 1.0 MeV
| 2.12248E-13 |
4.33174E-04 |
| Pu-239 with 0.0253 eV
| 2.80091E-09 |
3.82675E-04 |
| Pu-239 with 1.0 MeV
| 1.53046E-09 |
6.84164E-04 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|