Basic Info

Fission Yield


element
Information about Tin-133:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV .00000E+00 1.45876E-03
U-235 with 1.0 MeV .00000E+00 1.55773E-03
U-238 with 1.0 MeV 1.32191E-02 1.32373E-02
Pu-239 with 0.0253 eV 3.15029E-04 3.15047E-04
Pu-239 with 1.0 MeV 2.48488E-04 2.48502E-04
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)