50-Sn-121
basic
fission yield
XS graphs
element
|
50-tin-121
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
1.28041E-04 |
| U-235 with 1.0 MeV
| .00000E+00 |
3.47154E-04 |
| U-238 with 1.0 MeV
| 1.39696E-09 |
4.30557E-04 |
| Pu-239 with 0.0253 eV
| 3.64427E-07 |
3.76795E-04 |
| Pu-239 with 1.0 MeV
| 5.33546E-07 |
6.73465E-04 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
7.10713E-06 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.75597E-05 |
| U-238 with 1.0 MeV
| 3.90926E-09 |
1.16804E-05 |
| Pu-239 with 0.0253 eV
| 8.79976E-07 |
2.62338E-05 |
| Pu-239 with 1.0 MeV
| 1.49307E-06 |
4.77587E-05 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|