Basic Info

Fission Yield


element
Information about Cerium-145:

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 3.74219E-02
U-238 with 1.0 MeV 1.74404E-04 3.75587E-02
Pu-239 with 0.0253 eV 5.50336E-03 2.98443E-02
Pu-239 with 1.0 MeV 4.88463E-03 2.95892E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)