Basic Info

Fission Yield


element
Information about Cerium-148:

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 1.52382E-02
U-238 with 1.0 MeV 1.07678E-02 2.05906E-02
Pu-239 with 0.0253 eV 1.10841E-02 1.22569E-02
Pu-239 with 1.0 MeV 1.09137E-02 1.23622E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)