Basic Info
Fission Yield
n-XS summary
element
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Information about Tin-117:
 |  |  | | | Wikipedia | Neutron Cross Sections | X-Ray Transitions | X-Ray Attenuation |
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)
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