Basic Info

Fission Yield


element
Information about Arsenic-74:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 2.55541E-13 2.55541E-13
U-235 with 1.0 MeV 3.65630E-13 3.65630E-13
U-238 with 1.0 MeV 2.86338E-16 2.86338E-16
Pu-239 with 0.0253 eV 3.12890E-12 3.12890E-12
Pu-239 with 1.0 MeV 6.97186E-12 6.97186E-12
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)