Environmentally assisted cracking in light water reactors: Semiannual report, April--September 1987: Volume 5

Technical Report · Wed Feb 01 04:00:00 EST 1989

DOI:https://doi.org/10.2172/6372584· OSTI ID:6372584

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 April to September 1987. The stress corrosion cracking (SCC) behavior of Types 304, 316NG, and 347 stainless steel (SS) was investigated by means of slow-strain-rate and fracture-mechanics crack-growth-rate tests in high-temperature water. The relative susceptibility of the solution-annealed Type 304 SS to crack initiation was determined in water with two dissolved-oxygen concentrations. The effect 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 susceptibility of several heats of different grades of low-alloy steel to transgranular SCC was explored in slow-strain-rate tests at 289/degree/C, and the variation in the crack growth rates was attributed to differences in the sulfur content and sulfide inclusion distributions in the materials. 91 refs., 27 figs., 13 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: 6372584
• Report Number(s): NUREG/CR-4667-Vol.5; ANL-88-32-Vol.5; ON: TI89008096
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
COPPER
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRACKS
DOCUMENT TYPES
ELEMENTS
FATIGUE
FRACTURE MECHANICS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IMPURITIES
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MECHANICS
METALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NIOBIUM ADDITIONS
NIOBIUM ALLOYS
PROGRESS REPORT
PWR TYPE REACTORS
REACTORS
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEEL-347
STAINLESS STEELS
STEEL-CR17NI12MO3
STEEL-CR19NI10
STEELS
STRESS CORROSION
SULFUR CONTENT
TEMPERATURE EFFECTS
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS