Basic Info

Fission Yield


element
Information about Zinc-77:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 3.05932E-05 3.14086E-05
U-235 with 1.0 MeV 1.51302E-04 1.57654E-04
U-238 with 1.0 MeV 2.31671E-05 2.51611E-05
Pu-239 with 0.0253 eV 1.62153E-05 1.64718E-05
Pu-239 with 1.0 MeV 3.35902E-05 3.42545E-05
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)