Basic Info

Fission Yield


element
Information about Bromine-94:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 1.63963E-06 1.63997E-06
U-235 with 1.0 MeV 4.48799E-06 4.48912E-06
U-238 with 1.0 MeV 3.49810E-05 3.50244E-05
Pu-239 with 0.0253 eV 1.81059E-07 1.81075E-07
Pu-239 with 1.0 MeV 3.13095E-07 3.13124E-07
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)