Basic Info

Fission Yield


element
Information about Barium-144:

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 4.15963E-02
U-238 with 1.0 MeV 3.20286E-02 4.38549E-02
Pu-239 with 0.0253 eV 1.96556E-02 2.09772E-02
Pu-239 with 1.0 MeV 1.92809E-02 2.04245E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)