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In-situ heat treatment and polythionic acid testing of Inconel 600 Row 1 steam-generator U-bends. Final report. [PWR]

Technical Report ·
OSTI ID:6217446
U-bend leakage in Row 1 steam generator tubes has been reported at some operating plants. The leakage in these U-bends has been attributed to stress corrosion cracking that initiated at the ID surface of the tubes. The objective of Project S191-3 is to demonstrate the feasibility of heating the U-bends from the bore of the tube to a temperature that will reduce the residual stresses at the U-bend and thereby provide added resistance to stress corrosion. A number of U-bends fabricated from 3/4-inch and 7/8-inch O.D. mill annealed Inconel Alloy 600 tubing were heated to 788/sup 0/C (1450/sup 0/F) for 15 minutes using specially designed electrical resistance heaters. The results of these tests showed that the resistance heaters were capable of heating the U-bends to the desired temperatures and thus cause a significant reduction in the residual stresses. However, a desired improvement in microstructure was not detected. No significant distortion in the U-bends was detected, but the tube support plate was heated sufficiently to possibly cause unacceptable local thermally induced stresses.
Research Organization:
Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
OSTI ID:
6217446
Report Number(s):
EPRI-NP-3056; ON: DE83902271
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALLOYS
BOILERS
CHROMIUM ALLOYS
FEASIBILITY STUDIES
HEAT TREATMENTS
HYDROGEN COMPOUNDS
INCONEL 600
INCONEL ALLOYS
INORGANIC ACIDS
IRON ALLOYS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTORS
RESIDUAL STRESSES
STEAM GENERATORS
STRESSES
SULFUR COMPOUNDS
TEST FACILITIES
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS