Long-term performance of materials used for high-level waste packaging. Annual report, year four, April 1985-March 1986. Volume 4
Technical Report
·
OSTI ID:5500588
- comps.
As part of the information needed by the Nuclear Regulatory Commission to assess the Department of Energy's application to construct geologic repositories for high-level radioactive waste, Battelle's Columbus Division is investigating the long-term performance of materials used for high-level waste packages. Waste form studies have been directed toward investigating spent fuel leaching/dissolution behavior. The experimental validation of a glass dissolution/reprecipitation model has been concluded. Experiments are generating data on UO/sub 2/ and spent-fuel leach rates in simulated anoxic groundwaters, and initial data indicate that only brine leachants contain any measurable levels of uranium. The influence of groundwater species on the susceptibility of cast steel to pitting corrosion and stress-corrosion cracking is being studied by electrochemical techniques. Potential cracking agents are being investigated by slow strain rate experiments. The pitting-corrosion model was further developed, taking into account cation dissolution at the pit base and chemically active pit walls. Groundwater-radiolysis modeling has continued, with the description being extended to include additional species. Spent-fuel specimens are being used in integral tests with flowing simulated groundwater to study the role of cladding in radionuclide release and to identify possible combined-effects processes. This report documents investigations performed during the period April 1985 through March 1986.
- Research Organization:
- Battelle Columbus Labs., OH (USA)
- OSTI ID:
- 5500588
- Report Number(s):
- NUREG/CR-4379-Vol.4; BMI-2128-Vol.4; ON: TI86901560
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052002 -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360105* -- Metals & Alloys-- Corrosion & Erosion
360604 -- Materials-- Corrosion
Erosion
& Degradation
ACTINIDE COMPOUNDS
ALLOYS
BOROSILICATE GLASS
CHALCOGENIDES
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CONTAINERS
CORROSION
DECOMPOSITION
DISSOLUTION
ENERGY SOURCES
FUELS
GLASS
GROUND WATER
HYDROGEN COMPOUNDS
IRON ALLOYS
IRON BASE ALLOYS
LEACHING
MANAGEMENT
MATERIALS
MATERIALS TESTING
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PACKAGING
PERFORMANCE
PITTING CORROSION
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOACTIVE WASTE DISPOSAL
RADIOLYSIS
REACTOR MATERIALS
RESEARCH PROGRAMS
SEPARATION PROCESSES
SPENT FUELS
STEELS
STRESS CORROSION
TESTING
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WASTE DISPOSAL
WASTE FORMS
WASTE MANAGEMENT
WATER
WATER CHEMISTRY
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360105* -- Metals & Alloys-- Corrosion & Erosion
360604 -- Materials-- Corrosion
Erosion
& Degradation
ACTINIDE COMPOUNDS
ALLOYS
BOROSILICATE GLASS
CHALCOGENIDES
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CONTAINERS
CORROSION
DECOMPOSITION
DISSOLUTION
ENERGY SOURCES
FUELS
GLASS
GROUND WATER
HYDROGEN COMPOUNDS
IRON ALLOYS
IRON BASE ALLOYS
LEACHING
MANAGEMENT
MATERIALS
MATERIALS TESTING
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PACKAGING
PERFORMANCE
PITTING CORROSION
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOACTIVE WASTE DISPOSAL
RADIOLYSIS
REACTOR MATERIALS
RESEARCH PROGRAMS
SEPARATION PROCESSES
SPENT FUELS
STEELS
STRESS CORROSION
TESTING
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WASTE DISPOSAL
WASTE FORMS
WASTE MANAGEMENT
WATER
WATER CHEMISTRY