The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design
and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final
repository site. Several areas of analysis require detailed information concerning the time-dependent behavior
of radioactive nuclides including (1) neutron/gamma-ray sources for shielding studies, (2) fissile/absorber
concentrations for criticality safety determinations, (3) residual decay heat predictions for thermal