Open AccessDisposal criticality analysis methodology for fissile waste forms
Author(s) -
J.W. Davis,
P Gottlieb
Publication year - 1998
Language(s) - English
Resource type - Reports
DOI - 10.2172/658246
Subject(s) - criticality , fissile material , plutonium , radioactive waste , mox fuel , waste management , spent nuclear fuel , environmental science , nuclear engineering , enriched uranium , high level waste , uranium , engineering , neutron , materials science , radiochemistry , chemistry , nuclear physics , physics , metallurgy
A general methodology has been developed to evaluate the criticality potential of the wide range of waste forms planned for geologic disposal. The range of waste forms include commercial spent fuel, high level waste, DOE spent fuel (including highly enriched), MOX using weapons grade plutonium, and immobilized plutonium. The disposal of these waste forms will be in a container with sufficiently thick corrosion resistant barriers to prevent water penetration for up to 10,000 years. The criticality control for DOE spent fuel is primarily provided by neutron absorber material incorporated into the basket holding the individual assemblies. For the immobilized plutonium, the neutron absorber material is incorporated into the waste form itself. The disposal criticality analysis methodology includes the analysis of geochemical and physical processes that can breach the waste package and affect the waste forms within. The basic purpose of the methodology is to guide the criticality control features of the waste package design, and to demonstrate that the final design meets the criticality control licensing requirements. The methodology can also be extended to the analysis of criticality consequences (primarily increased radionuclide inventory), which will support the total performance assessment for the respository