Basic Info

Fission Yield

n-XS summary


element
Information about Strontium-87:

WikipediaNeutron Cross SectionsX-Ray TransitionsX-Ray Attenuation

Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 3.59883E-08 2.55433E-02
U-235 with 1.0 MeV 1.17237E-08 2.47030E-02
U-238 with 1.0 MeV 2.17853E-10 1.58800E-02
Pu-239 with 0.0253 eV 8.22204E-08 9.89145E-03
Pu-239 with 1.0 MeV 5.81214E-08 1.00277E-02

Fission Yields to Meta State
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 8.32183E-09 8.32288E-09
U-235 with 1.0 MeV 2.35997E-09 2.36023E-09
U-238 with 1.0 MeV 4.38535E-11 4.38542E-11
Pu-239 with 0.0253 eV 1.90124E-08 1.90176E-08
Pu-239 with 1.0 MeV 1.16998E-08 1.17031E-08
CSWEG, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991)