CX-270398: Simulated Used Nuclear Fuel Dissolution as a Function of Fuel Chemistry and Near Field Conditions – Washington State University

The Washington State University in collaboration with Pacific Northwest National Laboratory and the University of Sheffield, proposes to explore the effects of 1) fuel microstructure and chemistry using single- and multi-species doping, 2) cladding presence, and 3) corroded canister and/or overpack material, on UO2 dissolution and corrosion as a function of relevant parameters to include, for example, temperature, pH, and irradiation (or proxy for it). Tasks include: 1. Synthesis and microstructural characterization of doped UO2 materials; 2. Batch test, Single-pass-flow and related dissolution experiments on doped UO2 coupons in various water types, pH, and oxidizing/ reducing environments; 3. Dissolution testing of simulated interfaces of various fuel/ cladding/ canister combinations, including analysis by AFM techniques such as scanning electrochemical microscopy.