Basic Info

Fission Yield


element
Information about Arsenic-86:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 8.92531E-04 9.47220E-04
U-235 with 1.0 MeV 1.01427E-03 1.02420E-03
U-238 with 1.0 MeV 1.41409E-03 1.47943E-03
Pu-239 with 0.0253 eV 1.07325E-04 1.07728E-04
Pu-239 with 1.0 MeV 1.45474E-04 1.46044E-04
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)