Basic Info
Fission Yield
n-XS summary
element
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Information about Tin-119:
 |  |  | | | 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 |
1.21606E-04 |
| U-235 with 1.0 MeV
| .00000E+00 |
3.40521E-04 |
| U-238 with 1.0 MeV
| 3.54977E-12 |
3.57637E-04 |
| Pu-239 with 0.0253 eV
| 6.47886E-09 |
3.90757E-04 |
| Pu-239 with 1.0 MeV
| 8.20108E-09 |
6.32049E-04 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 0.0253 eV
| .00000E+00 |
5.10153E-07 |
| U-235 with 1.0 MeV
| .00000E+00 |
1.32673E-06 |
| U-238 with 1.0 MeV
| 1.34401E-11 |
1.11312E-06 |
| Pu-239 with 0.0253 eV
| 2.12001E-08 |
2.03757E-06 |
| Pu-239 with 1.0 MeV
| 3.10508E-08 |
3.27181E-06 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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