Intergranular attack and stress corrosion cracking propagation behavior of alloy 600 in high-temperature caustic solution
- Central Research Inst. of the Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.
The effect of stress intensity factors (K) at the intergranular attack and stress corrosion crack (IGA/SCC) tips on the IGA/SCC propagation behavior of steam generator (SG) tubing was studied under accelerated test conditions. Values of K at the IGA/SCC crack tips were calculated using the statically indeterminate model. Based upon analysis of those factors, the double-cantilever beam (DCB) and SG model boiler tests were carried out to evaluate the effect of stress intensity on IGA/SCC crack propagation. K at the crack tips increased with increasing crack length. For a long crack, K decreased with an increasing number of cracks. However, for a short crack, K decreased slightly with an increasing number of cracks. DCB test results showed the IGA/SCC crack velocity of alloy 600 (UNS N06600) increased gradually with increasing K in the range from 15 MPa[radical]m to [approximately]60 MPa[radical]m. This is the range relevant to IGA/SCC crack tips of typical SG tubes under operating conditions of Pressurized-water reactors. Metallographic examination of tubes removed from the SG model boiler, fouled with 10 ppm sodium hydroxide (NaOH), showed IGA/SCC propagation rates were almost constant in the tested range of K.
- OSTI ID:
- 6199663
- Journal Information:
- Corrosion, Journal Name: Corrosion Vol. 55:6; ISSN 0010-9312; ISSN CORRAK
- Country of Publication:
- United States
- Language:
- English
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Book
·
Fri Sep 01 00:00:00 EDT 1995
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OSTI ID:99552
Intergranular stress corrosion cracking initiation and growth in mill-annealed Alloy 600 tubing in high-temperature caustic
Journal Article
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Wed Jul 01 00:00:00 EDT 1998
· Corrosion
·
OSTI ID:634552
Mechanisms of stress corrosion cracking and intergranular attack in Alloy 600 in high temperature caustic and pure water
Conference
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Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6216507
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOY-NI76CR15FE8
ALLOYS
ALUMINIUM ADDITIONS
ALUMINIUM ALLOYS
BOILERS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
ENRICHED URANIUM REACTORS
FRACTURE MECHANICS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INCONEL 600
INCONEL ALLOYS
IRON ALLOYS
MATERIALS
MECHANICS
METALLOGRAPHY
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIMONIC
POWER REACTORS
PWR TYPE REACTORS
REACTORS
STEAM GENERATORS
STRESS CORROSION
STRESS INTENSITY FACTORS
THERMAL REACTORS
TITANIU
TITANIUM ADDITIONS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOY-NI76CR15FE8
ALLOYS
ALUMINIUM ADDITIONS
ALUMINIUM ALLOYS
BOILERS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
ENRICHED URANIUM REACTORS
FRACTURE MECHANICS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INCONEL 600
INCONEL ALLOYS
IRON ALLOYS
MATERIALS
MECHANICS
METALLOGRAPHY
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIMONIC
POWER REACTORS
PWR TYPE REACTORS
REACTORS
STEAM GENERATORS
STRESS CORROSION
STRESS INTENSITY FACTORS
THERMAL REACTORS
TITANIU
TITANIUM ADDITIONS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS