Basic Info
Fission Yield
n-XS summary
element
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Information about Tin-116:
 |  |  | | | 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 |
7.39913E-10 |
| U-235 with 1.0 MeV
| .00000E+00 |
7.61706E-10 |
| U-238 with 1.0 MeV
| 1.92008E-16 |
1.05125E-11 |
| Pu-239 with 0.0253 eV
| 5.90188E-12 |
2.54140E-08 |
| Pu-239 with 1.0 MeV
| 5.37160E-12 |
2.78137E-08 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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