Basic Info

Fission Yield


element
Information about Tin-136:

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 2.65948E-07
U-235 with 1.0 MeV .00000E+00 4.48817E-07
U-238 with 1.0 MeV 2.91742E-05 2.91782E-05
Pu-239 with 0.0253 eV 1.59051E-08 1.59053E-08
Pu-239 with 1.0 MeV 1.63049E-08 1.63051E-08
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)