Basic Info

Fission Yield


element
Information about Samarium-163:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-238 with 1.0 MeV 2.50293E-07 2.52709E-07
Pu-239 with 0.0253 eV 3.93127E-08 3.93449E-08
Pu-239 with 1.0 MeV 1.87057E-07 1.87246E-07
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)