50-Sn-122
basic
fission yield
n-XS summary
XS graphs
element
|
50-tin-122
Fission Yields
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
1.52990E-04 |
U-235 with 1.0 MeV
| .00000E+00 |
4.03677E-04 |
U-238 with 1.0 MeV
| 4.71552E-08 |
3.74284E-04 |
Pu-239 with 0.0253 eV
| 7.75251E-06 |
5.01762E-04 |
Pu-239 with 1.0 MeV
| 1.11434E-05 |
7.58650E-04 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|