Aqueous stress corrosion of candidate austenitic steels for iter structural applications

Technical Report · Thu Dec 31 04:00:00 EST 1992

OSTI ID:139235

French, D M; Soppet, W K; Kassner, T F

Susceptibility of Types 316NG and sensitized 304 stainless steels (SS) to SCC was investigated at temperatures of 60-289{degrees}C in slow-strain-rate-tensile (SSRT) tests in oxygenated water that simulates important parameters anticipated in first-wall/blanket systems. Several additional SSRT tests were performed on crevice specimens of Type 316NG SS in oxygenated water containing 100 ppb sulfate at temperatures between 150 and 289{degrees}C to establish the effect of temperature on SCC resistance. This steel exhibits good resistance to SCC under crevice and noncrevice conditions at temperatures <150{degrees}C in a nominal ITER coolant chemistry. In contrast, sensitized Type 304 SS exhibited intergranular stress corrosion cracking (IGSCC) at <100{degrees}C under crevice conditions. SSRT tests have been conducted on weldment specimens of Type 316L SS with matching filler metal under crevice conditions in oxygenated water containing 0.06-6.0 ppm chloride at 150-225{degrees}C. Most specimens fractured in the base metal, and several others fractured in the heat-affected zone (HAZ) of the weld, but none failed in the weld metal.

• Research Organization: Oak Ridge National Lab., TN (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 139235
• Report Number(s): DOE/ER--0313/13; ORNL/M--2722; ON: DE93013462
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
AUSTENITIC STEELS
BREEDING BLANKETS
CRACKING
CREVICE CORROSION
FIRST WALL
HEAT AFFECTED ZONE
ITER TOKAMAK
PROGRESS REPORT
STAINLESS STEEL-304
STAINLESS STEEL-316L
STAINLESS STEELS
STRESS CORROSION
TEMPERATURE RANGE 0273-0400 K
TEMPERATURE RANGE 0400-1000 K
TENSILE PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
WATER
WELDED JOINTS