Stress corrosion cracking of candidate structural materials under simulated first-wall/aqueous coolant environments
Conference
·
OSTI ID:6055066
Stress corrosion cracking (SCC) susceptibility of Types 316NG, 316, and 304 stainless steels (SS) was investigated in slow-strain-rate tests (SSRTs) in oxygenated water that simulates important parameters anticipated in first-wall/blanket systems. The water chemistry was based on a computer code which yielded the nominal concentrations of radiolytic species produced in an aqueous environment under ITER-type conditions. Actual SSRTs were performed in a less benign, more oxidizing reference environment at temperatures from 52 to 150{degree}C. Predominantly ductile fracture was observed in Type 316NG and nonsensitized Types 316 SS and 304 SS SSRT specimens strained to failure in a reference ITER water chemistry. The failure behavior of Type 304 SS specimens heat-treated to yield sensitization values of 2, 3, or 20 Coulomb (C)/cm{sup 2} by the electrochemical potentiokinetic reactivation (EPR) technique, demonstrated that the degree of sensitization had a dramatic effect on intergranular stress corrosion cracking (IGSCC) susceptibility. Ranking for resistance to SCC in simulated ITER water by electron microscopy and SSRT parameters, i.e., failure time, ultimate strength, total elongation and stress ratio is 304 SS (EPR = 20 <2 C/cm{sup 2}) < 316NG SS. 11 refs., 6 figs., 7 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6055066
- Report Number(s):
- CONF-901007-45; ON: DE91006370
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
AUSTENITIC STEELS
BREEDING BLANKETS
CHEMICAL REACTIONS
CHEMISTRY
CLOSED PLASMA DEVICES
COOLING SYSTEMS
CORROSION
CRACKS
CRYSTAL STRUCTURE
ELECTRON MICROSCOPY
ENERGY SYSTEMS
FIRST WALL
IRON ALLOYS
IRON BASE ALLOYS
ITER TOKAMAK
MATERIALS
MICROSCOPY
MICROSTRUCTURE
REACTOR COMPONENTS
SCANNING ELECTRON MICROSCOPY
STEELS
STRESS CORROSION
TEMPERATURE DEPENDENCE
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
WATER CHEMISTRY
360105 -- Metals & Alloys-- Corrosion & Erosion
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
AUSTENITIC STEELS
BREEDING BLANKETS
CHEMICAL REACTIONS
CHEMISTRY
CLOSED PLASMA DEVICES
COOLING SYSTEMS
CORROSION
CRACKS
CRYSTAL STRUCTURE
ELECTRON MICROSCOPY
ENERGY SYSTEMS
FIRST WALL
IRON ALLOYS
IRON BASE ALLOYS
ITER TOKAMAK
MATERIALS
MICROSCOPY
MICROSTRUCTURE
REACTOR COMPONENTS
SCANNING ELECTRON MICROSCOPY
STEELS
STRESS CORROSION
TEMPERATURE DEPENDENCE
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
WATER CHEMISTRY