Basic Info

Fission Yield


element
Information about Zinc-81:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 6.39857E-07 6.39995E-07
U-235 with 1.0 MeV 1.94913E-06 1.94982E-06
U-238 with 1.0 MeV 1.00017E-05 1.00099E-05
Pu-239 with 0.0253 eV 1.41046E-07 1.41063E-07
Pu-239 with 1.0 MeV 1.63049E-07 1.63074E-07
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)