Influence of iodine on the strain and rupture behavior of Zircaloy-4 cladding tubes at high temperatures
Creators
Description
The stress corrosion cracking (SCC) behavior of short tubular Zircaloy-4 specimens by the action of iodine (initial iodine concentration: 0.1 to 10 mg/cm$sup 3$) was investigated out-of-pile between 600 and 1100$degree$C under inert gas conditions. The Zircaloy cladding tube was used as-received and with an inner preliminary oxidation. Moreover, the influence of the uranium oxide (UO$sub 2$) oxygen potential on the SCC behavior was studied. The burst and creep-rupture tests (time-to-rupture $less than equivalent to$15 min) clearly show that the deformation behavior of Zircaloy cladding tubes below 850$degree$C is heavily influenced by the presence of iodine. A failure of Zircaloy tubes takes place that is characterized by little deformation as compared to reference specimens without iodine. With decreasing temperature, the burst strain is greatly reduced. Scanning electron microscope examinations of the rupture surfaces of the cladding tubes show that in the presence of iodine and at burst temperatures below 850$degree$C the cracks in the cladding material are mainly intergranular followed by ductile residual rupture. By contrast, iodine-free specimens are exclusively subject to ductile failure. 48 refs
Additional details
Publishing Information
- Journal Title
- Am. Soc. Test. Mater., Spec. Tech. Publ.
- Journal Issue
- no.681
- Series
- Am. Soc. Test. Mater., Spec. Tech. Publ.
- ISSN
- 0066-0558
Conference
- Title
- 4. symposium on zirconium in the nuclear industry.
- Dates
- 27 - 29 Jun 1978.
- Place
- Stratford-on-Avon, UK.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11558778
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CREEP; FUEL ELEMENT FAILURE; HIGH TEMPERATURE; IODINE; LOSS OF COOLANT; PWR TYPE REACTORS; STRAINS; STRESS CORROSION; URANIUM DIOXIDE; VERY HIGH TEMPERATURE; ZIRCALOY 4
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; CORROSION; ELEMENTS; HALOGENS; MECHANICAL PROPERTIES; NONMETALS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- CONF-780637--.