Basic Info

Fission Yield

n-XS summary


element
Information about Molybdenum-99:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 7.77757E-04 6.11047E-02
U-235 with 1.0 MeV 1.90515E-05 5.71393E-02
U-238 with 1.0 MeV 1.80211E-06 6.19570E-02
Pu-239 with 0.0253 eV 1.68925E-04 6.14028E-02
Pu-239 with 1.0 MeV 1.13554E-04 5.98385E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)