Basic Info

Fission Yield


element
Information about Molybdenum-111:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 5.52871E-08 5.52877E-08
U-235 with 1.0 MeV 2.28892E-07 2.28897E-07
U-238 with 1.0 MeV 5.63592E-06 5.63660E-06
Pu-239 with 0.0253 eV 1.11036E-07 1.11036E-07
Pu-239 with 1.0 MeV 1.85055E-07 1.85056E-07
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)