Basic Info

Fission Yield


element
Information about Tellurium-119:

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 4.54927E-21
U-235 with 1.0 MeV .00000E+00 2.47710E-20
U-238 with 1.0 MeV 1.14643E-23 1.14643E-23
Pu-239 with 0.0253 eV 5.76440E-18 5.76440E-18
Pu-239 with 1.0 MeV 8.09536E-18 8.09536E-18

Fission Yields to Meta State
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV .00000E+00 1.48861E-20
U-235 with 1.0 MeV .00000E+00 9.37878E-20
U-238 with 1.0 MeV 4.34061E-23 4.34061E-23
Pu-239 with 0.0253 eV 1.88622E-17 1.88622E-17
Pu-239 with 1.0 MeV 3.06505E-17 3.06505E-17
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)