Basic Info
Fission Yield
n-XS summary
element
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Information about Tin-123:
 |  |  | | | 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 |
3.05863E-05 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.82511E-05 |
| U-238 with 1.0 MeV
| 3.59946E-07 |
1.32834E-05 |
| Pu-239 with 0.0253 eV
| 2.12991E-05 |
3.31093E-05 |
| Pu-239 with 1.0 MeV
| 4.14830E-05 |
6.49364E-05 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
1.28220E-04 |
| U-235 with 1.0 MeV
| .00000E+00 |
4.34270E-04 |
| U-238 with 1.0 MeV
| 1.28626E-07 |
3.95591E-04 |
| Pu-239 with 0.0253 eV
| 8.82065E-06 |
4.04297E-04 |
| Pu-239 with 1.0 MeV
| 1.48239E-05 |
7.93690E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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