Waste package materials testing for a salt repository: 1983 status summary report
Technical Report
·
OSTI ID:6825260
The United States plans to safely dispose of nuclear waste in deep, stable geologic formations. As part of these plans, the US Department of Energy is sponsoring research on the designing and testing of waste packages and waste package materials. This fiscal year 1983 status report summarizes recent results of waste package materials testing in a salt environment. The results from these tests will be used by waste package designers and performance assessment experts. Release characteristics data are available on two waste forms (spent fuel and waste-containing glass) that were exposed to leaching tests at various radiation levels, temperatures, pH, glass surface area to solution volume ratios, and brine solutions simulating expected salt repository conditions. Candidate materials tested for corrosion resistance and other properties include iron alloys; TI-CODE 12, the most promising titanium alloy for containment; and nickel alloys. In component interaction testing, synergistic effects have not ruled out any candidate material. 21 refs., 37 figs., 15 tabs.
- Research Organization:
- Battelle Memorial Inst., Columbus, OH (USA). Office of Nuclear Waste Isolation
- DOE Contract Number:
- AC02-83CH10140
- OSTI ID:
- 6825260
- Report Number(s):
- BMI/ONWI-583; ON: DE87005939
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052002* -- Nuclear Fuels-- Waste Disposal & Storage
053000 -- Nuclear Fuels-- Environmental Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
360604 -- Materials-- Corrosion
Erosion
& Degradation
ALLOYS
BOROSILICATE GLASS
BRINES
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CORROSION RESISTANCE
DATA
DECOMPOSITION
DISSOLUTION
ELECTROMAGNETIC RADIATION
ENERGY SOURCES
EXPERIMENTAL DATA
FUELS
GAMMA RADIATION
GEOLOGIC DEPOSITS
GLASS
HIGH PRESSURE
HIGH TEMPERATURE
HIGH-LEVEL RADIOACTIVE WASTES
INFORMATION
IONIZING RADIATIONS
IRON ALLOYS
IRON BASE ALLOYS
LEACHING
MANAGEMENT
MATERIALS
MATERIALS TESTING
NICKEL ALLOYS
NUCLEAR FUELS
NUMERICAL DATA
PACKAGING
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIATIONS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
RADIOLYSIS
REACTOR MATERIALS
SALT DEPOSITS
SEPARATION PROCESSES
SIMULATION
SPENT FUELS
SURFACE AREA
SURFACE PROPERTIES
TESTING
TITANIUM ALLOYS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
053000 -- Nuclear Fuels-- Environmental Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
360604 -- Materials-- Corrosion
Erosion
& Degradation
ALLOYS
BOROSILICATE GLASS
BRINES
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CORROSION RESISTANCE
DATA
DECOMPOSITION
DISSOLUTION
ELECTROMAGNETIC RADIATION
ENERGY SOURCES
EXPERIMENTAL DATA
FUELS
GAMMA RADIATION
GEOLOGIC DEPOSITS
GLASS
HIGH PRESSURE
HIGH TEMPERATURE
HIGH-LEVEL RADIOACTIVE WASTES
INFORMATION
IONIZING RADIATIONS
IRON ALLOYS
IRON BASE ALLOYS
LEACHING
MANAGEMENT
MATERIALS
MATERIALS TESTING
NICKEL ALLOYS
NUCLEAR FUELS
NUMERICAL DATA
PACKAGING
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIATIONS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
RADIOLYSIS
REACTOR MATERIALS
SALT DEPOSITS
SEPARATION PROCESSES
SIMULATION
SPENT FUELS
SURFACE AREA
SURFACE PROPERTIES
TESTING
TITANIUM ALLOYS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES