Basic Info

Fission Yield


element
Information about Barium-143:

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 5.27633E-02
U-238 with 1.0 MeV 2.15407E-02 4.52717E-02
Pu-239 with 0.0253 eV 2.92710E-02 3.46523E-02
Pu-239 with 1.0 MeV 2.85978E-02 3.39621E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)