Basic Info

Fission Yield


element
Information about Cerium-150:

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 3.26486E-03
U-238 with 1.0 MeV 9.88048E-03 1.08149E-02
Pu-239 with 0.0253 eV 1.92594E-03 1.94774E-03
Pu-239 with 1.0 MeV 2.05708E-03 2.08660E-03
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)