Analysis of spent fuel performance in a geologic repository
Conference
·
OSTI ID:5778752
The Analytical REpository Source-Term (AREST) code developed for the US Department of Energy is being used to assess the time-dependent release rate of radionuclides from spent nuclear fuel disposed in geologic repositories. The Waste Package Release (WPR) submodule of AREST calculates the release from individual waste packages containing spent fuel based on site-specific design, solubility, corrosion, sorption, and mass transfer data. Under the open system conditions of a repository, there are two limiting release mechanisms: surface reaction control and transport control. In addition, a separate release case is defined for soluble radionuclides that are inventory limited. Mass transfer equations for each of these processes are incorporated into AREST. Four separate sources are identified in the AREST code based on inventory and release mechanism: UO/sub 2/ matrix (transport limited), gap (inventory limited), grain boundary (inventory limited, combined with gap), and cladding (transport limited). The calculated release of nuclides contained in the matrix (> 90% of the entire inventory) is controlled by UO/sub 2/ solubility or the solubility of a nuclide-bearing phase, whichever is lower.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA); USDOE, Washington, DC
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5778752
- Report Number(s):
- PNL-SA-13928; CONF-860418-9; ON: DE86011617
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052002 -- Nuclear Fuels-- Waste Disposal & Storage
054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
A CODES
ACTINIDE COMPOUNDS
ADSORPTION
CHALCOGENIDES
CHEMICAL REACTIONS
COMPUTER CODES
CORROSION
CRYSTAL STRUCTURE
DISSOLUTION
ENVIRONMENTAL TRANSPORT
FUEL ELEMENTS
GRAIN BOUNDARIES
MASS TRANSFER
MICROSTRUCTURE
NUCLEAR FACILITIES
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE
RADIOACTIVE WASTE FACILITIES
RADIONUCLIDE MIGRATION
REACTOR COMPONENTS
SOLUBILITY
SORPTION
SOURCE TERMS
SPENT FUEL ELEMENTS
TIME DEPENDENCE
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
A CODES
ACTINIDE COMPOUNDS
ADSORPTION
CHALCOGENIDES
CHEMICAL REACTIONS
COMPUTER CODES
CORROSION
CRYSTAL STRUCTURE
DISSOLUTION
ENVIRONMENTAL TRANSPORT
FUEL ELEMENTS
GRAIN BOUNDARIES
MASS TRANSFER
MICROSTRUCTURE
NUCLEAR FACILITIES
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE
RADIOACTIVE WASTE FACILITIES
RADIONUCLIDE MIGRATION
REACTOR COMPONENTS
SOLUBILITY
SORPTION
SOURCE TERMS
SPENT FUEL ELEMENTS
TIME DEPENDENCE
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES