38-Sr-86




Fission Yields
Fissile with Neutron Energy Yields ( sum = 2 )
Direct Accumulated
U-235 with 0.0253 eV 6.52853E-10 8.08308E-08
U-235 with 1.0 MeV 1.77919E-10 8.59750E-07
U-238 with 1.0 MeV 2.04239E-12 1.99244E-08
Pu-239 with 0.0253 eV 2.18069E-09 6.53359E-07
Pu-239 with 1.0 MeV 1.27037E-09 2.71194E-06

Total Cross Section
Elastic Scattering Cross Section
Total Inelastic Cross Section
(n,2n) Cross Section
(n,na) Cross Section
(n,np) Cross Section
Radiative Capture Cross Section
(n,p) Cross Section
(n,d) Cross Section
(n,t) Cross Section
(n,alpha) Cross Section
(n,2p) Cross Section

Element Sr