Basic Info

Fission Yield

n-XS summary


element
Information about Tellurium-123:

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 1.34970E-12
U-235 with 1.0 MeV .00000E+00 1.56830E-12
U-238 with 1.0 MeV 1.03658E-15 4.96127E-15
Pu-239 with 0.0253 eV 1.73969E-11 7.43238E-11
Pu-239 with 1.0 MeV 2.85488E-11 1.36642E-10

Fission Yields to Meta State
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV .00000E+00 1.03377E-12
U-235 with 1.0 MeV .00000E+00 1.24062E-12
U-238 with 1.0 MeV 3.92469E-15 3.92469E-15
Pu-239 with 0.0253 eV 5.69261E-11 5.69261E-11
Pu-239 with 1.0 MeV 1.08091E-10 1.08091E-10
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)