Basic Info

Fission Yield


element
Information about Samarium-158:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-238 with 1.0 MeV 6.45156E-05 1.72195E-04
Pu-239 with 0.0253 eV 2.91304E-04 3.41891E-04
Pu-239 with 1.0 MeV 5.06384E-04 6.16420E-04
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)