Used Fuel Disposal in Crystalline Rocks. FY15 Progress Report

Technical Report · Thu Aug 20 04:00:00 EDT 2015

DOI:https://doi.org/10.2172/1229704· OSTI ID:1229704

Wang, Yifeng ^[1]

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

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.

• Research Organization: Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 1229704
• Report Number(s): SAND--2015-10687R; 614881
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BENTONITE
CESIUM
COLLOIDS
DENSITY
DESORPTION
DIFFUSION
DISSOLUTION
EVALUATION
IGNEOUS ROCKS
METAMORPHIC ROCKS
PLUTONIUM
PROGRESS REPORT
RADIONUCLIDE MIGRATION
SORPTION
SPENT FUELS
TEMPERATURE DEPENDENCE
UNDERGROUND DISPOSAL
URANIUM