Basic Info

Fission Yield


element
Information about Zirconium-97:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 7.18085E-03 5.99541E-02
U-235 with 1.0 MeV 7.04590E-03 5.98385E-02
U-238 with 1.0 MeV 2.29688E-03 5.57417E-02
Pu-239 with 0.0253 eV 1.56656E-02 5.36591E-02
Pu-239 with 1.0 MeV 1.33305E-02 5.29568E-02
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)