Basic Info

Fission Yield


element
Information about Samarium-161:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-238 with 1.0 MeV 8.80031E-06 9.51795E-06
Pu-239 with 0.0253 eV 5.58181E-06 5.62756E-06
Pu-239 with 1.0 MeV 1.12534E-05 1.13665E-05
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)