Environmentally assisted cracking in light water reactors
Topics that have been considered during this year include (1) stress corrosion cracking (SCC) of austenitic stainless steels (SS), (2) fatigue of Type 316NG SS, and (3) SCC of ferritic steels used in reactor piping, pressure vessels, and steam generators. Constant-extension-rate-tests (CERTs) and crack-growth-rate (CGR) tests on 1TCT specimens were performed to quantify the effects of chromate, sulfate, chloride, and low levels of organic impurities on SCC of sensitized Type 304 and Type 316NG SS. Some organic substances were found to actually inhibit SCC of sensitized Type 304 SS. Fatigue tests on Type 316NG SS showed that even at 0.5 Hz the fatigue life in the environment is about half of that in air, and the reduction in life increases at lower frequencies. CGR tests on A533-Gr B pressure vessel steel are in progress on conventional specimens and composite specimens of A533-Gr B/Inconel-182/Inconel-600. Some of the specimens have been plated with either nickel or gold to reduce contact between the surface of low-alloy steel and the environment. Comparison of the results from the bare and plated specimens will provide insight into whether electron transfer through the oxide film on the bulk surface of the ferritic steel is important in the overall SCC process. 49 refs., 16 figs., 9 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5318685
- Report Number(s):
- CONF-8910222-10; ON: DE90003799
- Country of Publication:
- United States
- Language:
- English
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Environmentally assisted cracking in light water reactors. Semiannual report, April--September 1991: Volume 13
Environmentally assisted cracking in light water reactors
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42 ENGINEERING
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ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHEMISTRY
COOLING SYSTEMS
CRACKING
DATA
DECOMPOSITION
ELECTRIC CONDUCTIVITY
ELECTRICAL PROPERTIES
ELECTROMAGNETIC RADIATION
ENERGY SYSTEMS
ENERGY TRANSFER
EXPERIMENTAL DATA
FAILURE MODE ANALYSIS
FATIGUE
FEEDWATER
FLUID MECHANICS
FRACTURE MECHANICS
GAMMA RADIATION
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
INFORMATION
IONIZING RADIATIONS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MATHEMATICAL MODELS
MEASURING METHODS
MECHANICAL PROPERTIES
MECHANICS
METALLURGY
NUMERICAL DATA
ORGANIC COMPOUNDS
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
PWR TYPE REACTORS
PYROLYSIS
RADIATIONS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
SERVICE LIFE
SIMULATION
STEELS
STRUCTURAL CHEMICAL ANALYSIS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
THERMAL CRACKING
THERMAL FATIGUE
THERMOCHEMICAL PROCESSES
WATER
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS