Basic Info

Fission Yield


element
Information about Barium-153:

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 9.96375E-14
U-238 with 1.0 MeV 1.14441E-10 1.14441E-10
Pu-239 with 0.0253 eV 5.37452E-14 5.37452E-14
Pu-239 with 1.0 MeV 9.37442E-14 9.37442E-14
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)