Basic Info
Fission Yield
element
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Information about Lanthanum-146:
 |  |  | | | Wikipedia | Neutron Cross Sections | X-Ray Transitions | X-Ray Attenuation |
Fission Yields
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 1.0 MeV
| .00000E+00 |
1.07434E-02 |
| U-238 with 1.0 MeV
| 1.68679E-03 |
2.67434E-02 |
| Pu-239 with 0.0253 eV
| 2.68121E-03 |
4.56955E-03 |
| Pu-239 with 1.0 MeV
| 2.63280E-03 |
4.69487E-03 |
Fission Yields to Meta State
| Fissile with Neutron Energy |
Yields ( sum = 2 ) |
|---|
| Direct |
Accumulated |
|---|
| U-235 with 1.0 MeV
| .00000E+00 |
1.16471E-02 |
| U-238 with 1.0 MeV
| 5.87569E-03 |
5.87821E-03 |
| Pu-239 with 0.0253 eV
| 8.08898E-03 |
8.08904E-03 |
| Pu-239 with 1.0 MeV
| 9.17098E-03 |
9.17105E-03 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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