Long-term performance of materials used for high-level waste packaging. First quarterly report, year three April-June 1984. Volume 1

Technical Report · Sat Sep 01 04:00:00 EDT 1984

OSTI ID:6432788

Stahl, D; Miller, N E ^[1]

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1. comps.

As part of the Nuclear Regulatory Commission's requirement to assess the Department of Energy's application to construct geologic repositories for storing high-level radioactive waste, Battelle's Columbus Laboratories is investigating the long-term performance of materials used for high-level waste packaging. Devitrification severity of glass waste forms is being studied in terms of volume fraction of crystallization and crystal grain size. Glass-water contact during the heating and cooling periods of glass leaching experiments is being evaluated for its effect on the overall results of the isothermal period. Modeling efforts included the study of possible colloid formation and the change of water chemistry during glass dissolution. The electrochemical properties of container steels were found to be only slightly affected by the groundwater-species concentration, the presence of basalt rock, or the steels' cleanliness or microstructure. Hydrogen-embrittlement susceptibility may increase at expected repository temperatures. Results of the corrosion-modeling effort suggest that radiolysis may significantly affect general-corrosion kinetics. The water-radiolysis model was extended to account for more groundwater species and was used to predict the concentrations of two species in aqueous iron sulfate; results were compared with experimental data. A method was selected for performing uncertainty analyses of waste-package models. Integral experiments have been designed to address the combined effects of repository conditions on the waste package.

• Research Organization: Battelle Columbus Labs., OH (USA)
• OSTI ID: 6432788
• Report Number(s): NUREG/CR-3900-Vol.1; ON: TI85900254
• Country of Publication: United States
• Language: English

Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
360604 -- Materials-- Corrosion
Erosion
& Degradation
ALLOYS
BOROSILICATE GLASS
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CORROSION
DATA
DECOMPOSITION
DISSOLUTION
EMBRITTLEMENT
EXPERIMENTAL DATA
FRACTURE PROPERTIES
GLASS
GROUND WATER
HIGH-LEVEL RADIOACTIVE WASTES
HYDROGEN COMPOUNDS
HYDROGEN EMBRITTLEMENT
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
LEACHING
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
NUMERICAL DATA
OXYGEN COMPOUNDS
PACKAGING
PERFORMANCE
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RADIOLYSIS
RESEARCH PROGRAMS
SEPARATION PROCESSES
STEELS
TESTING
TIME DEPENDENCE
WASTE FORMS
WASTES
WATER
WATER CHEMISTRY