Basic Info

Fission Yield

n-XS summary


element
Information about Cadmium-111:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV .00000E+00 2.00221E-04
U-235 with 1.0 MeV .00000E+00 4.30585E-04
U-238 with 1.0 MeV 1.41405E-14 8.02051E-04
Pu-239 with 0.0253 eV 2.85192E-10 3.03603E-03
Pu-239 with 1.0 MeV 2.07326E-10 3.55426E-03

Fission Yields to Meta State
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV .00000E+00 4.98507E-12
U-235 with 1.0 MeV .00000E+00 3.40320E-12
U-238 with 1.0 MeV 5.35387E-14 5.35387E-14
Pu-239 with 0.0253 eV 9.33202E-10 9.33202E-10
Pu-239 with 1.0 MeV 7.84974E-10 7.84974E-10
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)