Basic Info

Fission Yield


element
Information about Lanthanum-142:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 1.0 MeV .00000E+00 5.66976E-02
U-238 with 1.0 MeV 4.07177E-05 4.72968E-02
Pu-239 with 0.0253 eV 3.50524E-03 4.97969E-02
Pu-239 with 1.0 MeV 3.19984E-03 4.77171E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)