Basic Info

Fission Yield

n-XS summary


element
Information about Neodymium-146:

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 2.90270E-02
U-238 with 1.0 MeV 9.92162E-10 3.39528E-02
Pu-239 with 0.0253 eV 2.00065E-06 2.46206E-02
Pu-239 with 1.0 MeV 1.37042E-06 2.43620E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)