Basic Info
Fission Yield
element
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Information about Lanthanum-149:
 |  |  | | | 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 |
8.42384E-04 |
| U-238 with 1.0 MeV
| 3.84891E-03 |
4.14006E-03 |
| Pu-239 with 0.0253 eV
| 2.03626E-04 |
2.04452E-04 |
| Pu-239 with 1.0 MeV
| 2.76014E-04 |
2.77189E-04 |
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)
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