Used Fuel Disposal in Crystalline Rocks. FY15 Progress Report
- 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 Lab. (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; TRN: US1600177
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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