Basic Info

Fission Yield

n-XS summary


element
Information about Samarium-154:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-238 with 1.0 MeV 1.81212E-06 2.13528E-03
Pu-239 with 0.0253 eV 1.99285E-04 2.71589E-03
Pu-239 with 1.0 MeV 1.63380E-04 2.75441E-03
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)