Basic Info

Fission Yield


element
Information about Bromine-78:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 2.18951E-13 2.18951E-13
U-235 with 1.0 MeV 2.18902E-13 2.18902E-13
U-238 with 1.0 MeV 2.51311E-16 2.51311E-16
Pu-239 with 0.0253 eV 3.53114E-12 3.53114E-12
Pu-239 with 1.0 MeV 2.88087E-12 2.88087E-12
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)