Basic Info

Fission Yield


element
Information about Bromine-89:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 1.20589E-02 1.31903E-02
U-235 with 1.0 MeV 1.68799E-02 1.81552E-02
U-238 with 1.0 MeV 1.33800E-02 1.70268E-02
Pu-239 with 0.0253 eV 3.44132E-03 3.54241E-03
Pu-239 with 1.0 MeV 3.56801E-03 3.68132E-03
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)