Basic Info

Fission Yield

n-XS summary


element
Information about Cerium-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 5.67012E-02
U-238 with 1.0 MeV 6.08713E-08 4.72968E-02
Pu-239 with 0.0253 eV 5.81188E-05 4.98550E-02
Pu-239 with 1.0 MeV 3.82216E-05 4.77553E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)