Stress corrosion cracking of candidate structural materials under simulated first-wall/aqueous coolant environments
Description
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)/cm2 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/cm2) < 316NG SS. 11 refs., 6 figs., 7 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE91006370; NTIS; INIS; US Govt. Printing Office Dep.Files
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Additional details
Publishing Information
- Imprint Pagination
- 31 p.
- Report number
- CONF-901007--45
Conference
- Title
- 9. topical meeting on technology of fusion energy.
- Dates
- 7-11 Oct 1990.
- Place
- Oak Brook, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22032788
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUSTENITIC STEELS; BREEDING BLANKETS; CRACKS; FIRST WALL; ITER TOKAMAK; MICROSTRUCTURE; SCANNING ELECTRON MICROSCOPY; STRESS CORROSION; TEMPERATURE DEPENDENCE; THERMONUCLEAR REACTOR COOLING; THERMONUCLEAR REACTOR MATERIAL; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CLOSED PLASMA DEVICES; COOLING SYSTEMS; CORROSION; CRYSTAL STRUCTURE; ELECTRON MICROSCOPY; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MICROSCOPY; STEELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES; WATER TREATMENT
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38