Basic Info

Fission Yield


element
Information about Cerium-149:

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 7.43377E-03
U-238 with 1.0 MeV 1.10346E-02 1.51266E-02
Pu-239 with 0.0253 eV 5.04925E-03 5.25132E-03
Pu-239 with 1.0 MeV 5.64156E-03 5.91552E-03
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)