Open AccessStorage of assemblies containing mixed-oxide fuel
Author(s) -
R.T. Primm,
J.C. Ryman,
S.B. Ludwig
Publication year - 1997
Language(s) - English
Resource type - Reports
DOI - 10.2172/582213
Subject(s) - mox fuel , uranium oxide , spent nuclear fuel , oxide , uranium , mixed oxide , nuclear fuel , uranium dioxide , nuclear engineering , waste management , process engineering , environmental science , computer science , materials science , engineering , metallurgy
Both fresh and spent mixed-oxide (MOX) assemblies exhibit physical characteristics that will necessitate additional measurements and analyses beyond those that are done for low-enriched uranium (LEU) assemblies. While none of these analyses or measurements require technological development, estimates for disposition costs and schedules must account for these factors. This report identifies those nuclear engineering analyses that will be required to demonstrate acceptability of MOX fuel assembly storage