Basic Info

Fission Yield


element
Information about Cerium-136:

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 2.05902E-17
U-238 with 1.0 MeV 2.93175E-21 2.93175E-21
Pu-239 with 0.0253 eV 3.94822E-15 3.94822E-15
Pu-239 with 1.0 MeV 4.28072E-15 4.28072E-15
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)