Sensitization and SCC (stress corrosion cracking) study on thermally treated inconel 600
Stress corrosion cracking (SCC) was recently discovered to be the major cause of failure in Inconel 600 used in steam generator (SG) tubes of pressurized water reactors (PWRs). The failure of the Three Mile Island SG tubes has been attributed to low-temperature SCC in the sulfur-contaminated environment under cold shutdown conditions. Bandy et al. found that even in the 10{sup {minus}6} M Na{sub 2}S{sub 2}O{sub 3} (or N{sub 2}S{sub 4}O{sub 6}) environment, the SCC would still be observable. This study investigates the effect of thermal treatment on the sensitization of Inconel 600 and studies the SCC behavior of this alloy in a sulfur-contaminated environment (S{sub 2}O{sub 3}{sup {minus}2}) using constant load test. The results of this study can be used to correlate the SCC susceptibility to the degree of sensitization of Inconel 600 by defining a critical chromium concentration under the test conditions.
- OSTI ID:
- 5622207
- Report Number(s):
- CONF-880601-; CODEN: TANSA; TRN: 89-027780
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 56; Conference: American Nuclear Society annual meeting, San Diego, CA (USA), 12-16 Jun 1988; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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INCONEL 600
SENSITIZERS
PWR TYPE REACTORS
STEAM GENERATORS
TUBES
CRACKS
STRESS CORROSION
CHROMIUM
FAILURES
QUANTITY RATIO
SULFUR
TRANSMISSION ELECTRON MICROSCOPY
ALLOY-NI76CR15FE8
ALLOYS
ALUMINIUM ADDITIONS
ALUMINIUM ALLOYS
BOILERS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CORROSION RESISTANT ALLOYS
ELECTRON MICROSCOPY
ELEMENTS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INCONEL ALLOYS
IRON ALLOYS
MATERIALS
METALS
MICROSCOPY
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIMONIC
NONMETALS
REACTORS
REAGENTS
TITANIU
TITANIUM ADDITIONS
TRANSITION ELEMENTS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled