Basic Info

Fission Yield


element
Information about Barium-146:

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 7.39992E-03
U-238 with 1.0 MeV 2.40768E-02 2.50566E-02
Pu-239 with 0.0253 eV 1.87584E-03 1.88834E-03
Pu-239 with 1.0 MeV 2.05126E-03 2.06207E-03
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)