Basic Info

Fission Yield


element
Information about Lanthanum-137:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 1.0 MeV .00000E+00 5.74743E-10
U-238 with 1.0 MeV 1.27149E-12 1.27149E-12
Pu-239 with 0.0253 eV 2.56083E-08 2.56091E-08
Pu-239 with 1.0 MeV 2.39073E-08 2.39079E-08
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)