Basic Info

Fission Yield


element
Information about Zinc-74:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 2.30949E-06 3.54998E-06
U-235 with 1.0 MeV 7.65657E-06 1.48423E-05
U-238 with 1.0 MeV 3.26382E-07 9.62583E-07
Pu-239 with 0.0253 eV 3.69120E-06 4.92950E-06
Pu-239 with 1.0 MeV 1.14935E-05 1.63830E-05
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)