Effects of internal surface flaws, iodine concentration and temperature on the stress corrosion cracking behavior of Zircaloy-4 tubing (LWBR Development Program)
Technical Report
·
OSTI ID:7363742
Iodine stress corrosion cracking (SCC) in unirradiated stress-relieved Zircaloy-4 tubing specimens internally pressurized with argon gas to produce hoop stresses from 25,000 to 50,000 psi is evaluated experimentally in terms of the effects of internal surface flaws ranging from pits to grooves, of iodine concentrations between 0.05 and 4 mg/dm/sup 2/ Zircaloy surface and of test temperatures of 680/sup 0/, 720/sup 0/ and 750/sup 0/F on the time-to-failure. These data are analyzed in the framework of a fracture mechanics model for iodine vapor SCC. A reasonable correlation is demonstrated between minimum iodine SCC lifetime and surface flaw characteristics. Lifetime is determined to vary inversely with iodine concentration to the 3/4 power. An expression relating the iodine SCC threshold stress in Zircaloy-4 tubing to temperature, iodine concentration and surface flaw characteristics is presented. Test results are given corroborating the prediction expression for threshold stress.
- Research Organization:
- Bettis Atomic Power Lab., West Mifflin, Pa. (USA)
- OSTI ID:
- 7363742
- Report Number(s):
- WAPD-TM-1248
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
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36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BREEDER REACTORS
CHEMICAL REACTIONS
CORROSION
CORROSIVE EFFECTS
DEFECTS
ELEMENTS
FAILURES
FUEL CANS
HALOGENS
IODINE
LWBR TYPE REACTORS
NONMETALS
PERFORMANCE TESTING
REACTORS
STRESS CORROSION
TEMPERATURE DEPENDENCE
TESTING
THERMAL REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BREEDER REACTORS
CHEMICAL REACTIONS
CORROSION
CORROSIVE EFFECTS
DEFECTS
ELEMENTS
FAILURES
FUEL CANS
HALOGENS
IODINE
LWBR TYPE REACTORS
NONMETALS
PERFORMANCE TESTING
REACTORS
STRESS CORROSION
TEMPERATURE DEPENDENCE
TESTING
THERMAL REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS