Iodine stress-corrosion cracking in irradiated Zircaloy cladding. [PWR; BWR]
Conference
·
OSTI ID:6019532
Irradiated Zircaloy cladding specimens, which had experienced fluences from 0.1 to 6 x 10/sup 21/ n/cm/sup 2/ (E>0.1 MeV), were gas-pressure tested in an iodine environment to investigate their stress-corrosion cracking (SCC) susceptibility. The test temperatures and hoop stresses ranged from 320 to 360/sup 0/C and 150 to 500 MPa, respectively. The results indicate that irradiation, in general, increases the susceptibility of Zircaloy to iodine SCC. For specimens that experienced fluences >2 x 10/sup 21/ n/cm/sup 2/ (E>0.1 MeV), the 24-h failure stress was 177+-18 MPa, regardless of the preirradiation metallurgical condition. An analytical model for iodine SCC has been developed which agrees reasonably well with the test results.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6019532
- Report Number(s):
- CONF-790441--7
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CORROSION
CRACKS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL-CLADDING INTERACTIONS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTORS
STRESS CORROSION
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CORROSION
CRACKS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL-CLADDING INTERACTIONS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTORS
STRESS CORROSION
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS