50-Sn-117
basic
fission yield
n-XS summary
XS graphs
element
|
50-tin-117
Fission Yields
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
1.08339E-04 |
U-235 with 1.0 MeV
| .00000E+00 |
3.37964E-04 |
U-238 with 1.0 MeV
| 2.82391E-15 |
3.66012E-04 |
Pu-239 with 0.0253 eV
| 4.35508E-11 |
5.63143E-04 |
Pu-239 with 1.0 MeV
| 4.20079E-11 |
7.87357E-04 |
Fission Yields to Meta State
Fissile with Neutron Energy |
Yields ( sum = 2 ) |
Direct |
Accumulated |
U-235 with 0.0253 eV
| .00000E+00 |
9.65272E-07 |
U-235 with 1.0 MeV
| .00000E+00 |
2.97880E-06 |
U-238 with 1.0 MeV
| 1.06919E-14 |
3.20934E-06 |
Pu-239 with 0.0253 eV
| 1.42507E-10 |
5.12620E-06 |
Pu-239 with 1.0 MeV
| 1.59050E-10 |
7.14182E-06 |
CSWEG, ENDF/B-VI Summary Documentation,Report BNL-NCS-17541 (ENDF-201) (1991)
|