Basic Info

Fission Yield

n-XS summary


element
Information about Neodymium-147:

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 2.09611E-02
U-238 with 1.0 MeV 5.51646E-08 2.52979E-02
Pu-239 with 0.0253 eV 3.01898E-05 2.04281E-02
Pu-239 with 1.0 MeV 2.24368E-05 1.97817E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)