Basic Info

Fission Yield


element
Information about Zinc-71:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 4.49702E-10 6.80857E-08
U-235 with 1.0 MeV 1.65817E-09 5.05195E-07
U-238 with 1.0 MeV 2.32521E-11 4.47291E-08
Pu-239 with 0.0253 eV 3.82501E-09 2.43034E-07
Pu-239 with 1.0 MeV 1.96784E-08 1.78974E-06

Fission Yields to Meta State
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 1.94477E-09 9.04421E-09
U-235 with 1.0 MeV 8.23738E-09 6.10917E-08
U-238 with 1.0 MeV 1.15510E-10 4.80814E-09
Pu-239 with 0.0253 eV 1.65415E-08 4.16497E-08
Pu-239 with 1.0 MeV 9.77573E-08 2.83550E-07
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)