Characterization of irradiated zircaloys: susceptibility to stress-corrosion cracking. Interim report
Irradiated Zircaloy cladding specimens which experienced burnups from 6 to 30 MWd/kg U were gas-pressure tested in an iodine environment to investigate their stress-corrosion cracking (SCC) susceptibility. Several cladding sources were used in the investigation, and both PWR and BWR claddings were tested. The test temperatures ranged from 320 to 360/sup 0/C, and the test hoop stresses ranged from 150 to 500 MPa (22 to 72 ksi). Two iodine concentrations, 6.0 and 0.6 mg/cm/sup 2/, were used in the tests. Failure times ranged from 360 s (6 min) at high stresses to 5 x 10/sup 5/ s (142 h) at low stresses. For specimens that experienced a burnup of greater than or equal to 10 MWd/kg U, the 24-h failure stress was 177 +- 18 MPa (25.6 +- 2.6 ksi), regardless of the preirradiation metallurgical condition. Scanning electron microscopy and optical metallography were used to characterize the SCC failures. An analytical model for iodine SCC was developed which correlates reasonably well with the test results.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5796175
- Report Number(s):
- EPRI-NP-1155
- Country of Publication:
- United States
- Language:
- English
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360105* -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
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CRACKS
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210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
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210200 -- Power Reactors
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36 MATERIALS SCIENCE
360105* -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CORROSION
CORROSIVE EFFECTS
CRACKS
ELEMENTS
FAILURES
FUEL CANS
HALOGENS
IODINE
NONMETALS
PWR TYPE REACTORS
REACTORS
STRESS CORROSION
STRESSES
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
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ZIRCONIUM BASE ALLOYS