Used Fuel Disposal in Crystalline Rocks. FY15 Progress Report

Wang, Yifeng¹ 

[1] Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

关键词: IGNEOUS ROCKS;    METAMORPHIC ROCKS;    PROGRESS REPORT;    SPENT FUELS;    UNDERGROUND DISPOSAL;    EVALUATION;    BENTONITE;    URANIUM;    DIFFUSION;    DENSITY;    PLUTONIUM;    SORPTION;    DESORPTION;    COLLOIDS;    CESIUM;    RADIONUCLIDE MIGRATION;    DISSOLUTION;    TEMPERATURE DEPENDENCE;   

DOI  :  10.2172/1229704
RP-ID  :  SAND--2015-10687R
PID  :  OSTI ID: 1229704
Others  :  Other: 614881
Others  :  TRN: US1600177

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

The objective of the Crystalline Disposal R&D Work Package is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and computational capabilities to evaluate various disposal concepts in such media. Chapter headings are as follows: Fuel matrix degradation model and its integration with performance assessments, Investigation of thermal effects on the chemical behavior of clays, Investigation of uranium diffusion and retardation in bentonite, Long-term diffusion of U(VI) in bentonite: dependence on density, Sorption and desorption of plutonium by bentonite, Dissolution of plutonium intrinsic colloids in the presence of clay and as a function of temperature, Laboratory investigation of colloid-facilitated transport of cesium by bentonite colloids in a crystalline rock system, Development and demonstration of discrete fracture network model, Fracture continuum model and its comparison with discrete fracture network model.