Basic Info

Fission Yield


element
Information about Cerium-155:

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 6.97687E-08
U-238 with 1.0 MeV 4.19464E-06 4.19491E-06
Pu-239 with 0.0253 eV 8.50274E-09 8.50275E-09
Pu-239 with 1.0 MeV 1.60049E-08 1.60049E-08
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)