Environmentally assisted cracking in light water reactors: Semiannual report, October 1987--March 1988

Technical Report · Tue Aug 01 00:00:00 EDT 1989

DOI:https://doi.org/10.2172/5743783· OSTI ID:5743783

Shack, W. J.; Kassner, T. F.; Maiya, P. S.; Park, J. Y.; Ruther, W. E.

This report summarizes work performed by Argonne National Laboratory on environmentally assisted cracking in light water reactors during the six months from October 1987 through March 1988. The stress corrosion cracking (SCC) of Types 304, 316NG, 347, and CF3M cast stainless steels (SSs) was investigated by means of slow-strain-rate, crevice-bent-beam, and fracture-mechanics crack-growth-rate tests in high-temperature water. The effects of temperature and water chemistry on the crack growth behavior of Type 136NG and sensitized Type 304 SS were determined in long-term fracture-mechanics tests. The influence of dissolved copper and organic impurities on the SCC of sensitized Type 304 SS was also investigated. Fatigue tests are being conducted on Type 316NG SS in air at room temperature to provide baseline data for comparison with results that will be obtained in high-temperature water. The investigation of the susceptibility of several heats of different grades of low-alloy ferritic steels to transgranular SCC in slow-strain-rate tests was continued. 8 refs., 21 figs., 10 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5743783
• Report Number(s): NUREG/CR-4667-Vol.6; ANL-89/10-Vol.6; ON: TI89015614
• Country of Publication: United States
• Language: English

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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CONTAINERS
COPPER
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRYSTAL STRUCTURE
DOCUMENT TYPES
ELEMENTS
FAILURES
FATIGUE
FERRITIC STEELS
FRACTURES
GRAIN SIZE
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TREATMENTS
HIGH ALLOY STEELS
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
METALLURGICAL EFFECTS
METALS
MICROSTRUCTURE
NICKEL ALLOYS
NIOBIU
PROGRESS REPORT
PWR TYPE REACTORS
REACTOR VESSELS
REACTORS
SIZE
SOLUBILITY
STAINLESS STEEL-304
STAINLESS STEEL-347
STAINLESS STEELS
STEEL-CR18NI11NB
STEEL-CR19NI10
STEELS
STRESS CORROSION
TEMPERATURE EFFECTS
TENSILE PROPERTIES
TRANSITION ELEMENTS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS