Oxidation of advanced zirconium cladding alloys in steam at temperature 600-1200degC
Steinbrueck, Martin; Ver, Nora; Grosse, Mirco, E-mail: steinbrueck@imf.fzk.de
Proceedings of 2009 international congress on advances in nuclear power plants2009
Proceedings of 2009 international congress on advances in nuclear power plants2009
AbstractAbstract
[en] The oxidation kinetics of the classic pressurized water reactors (PWR) cladding alloy Zircaloy-4 has been extensively investigated over a wide temperature range from operational conditions to beyond design basis accident (BDBA) temperatures. In recent years, new cladding alloys optimized for longer operation and higher burn-up are used in western light water reactors (LWR). This paper presents the results of thermo-gravimetric tests with Zircaloy-4 as reference material, Duplex DX-D4, M5 (both AREVA), ZirloTM (Westinghouse) and the Russian E110 alloy. All materials were investigated in isothermal and transient tests in a thermal balance with steam furnace. Post-test analyses have been performed by light-microscopy and neutron radiography for investigation of the hydrogen absorbed by the metal. Strong and varying differences (up to 800%) in oxidation kinetics between the alloys were found up to 1000degC, where the breakaway effects play a role. Less but significant differences (ca. 30%) were observed at 1100 and 1200degC. Generally, the M5 alloy reveals the lowest oxidation rate over the temperature range investigated whereas the behavior of the other alloys is strongly dependent on temperature. A strong correlation was found between oxide scale structure and amount of absorbed hydrogen. (author)
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Atomic Energy Society of Japan, Tokyo (Japan); [2572 p.]; 2009; [10 p.]; ICAPP2009: 2009 international congress on advances in nuclear power plants; Tokyo (Japan); 10-14 May 2009; Available as CD-ROM Data in PDF format, Folder Name: FinalPaper, Paper ID: 9007.pdf; 16 refs., 9 figs., 3 tabs.
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Miscellaneous
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Conference
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Descriptors (DEC)
ALLOYS, ALLOY-ZR98SN-4, CHEMICAL ANALYSIS, CHEMICAL REACTIONS, CHROMIUM ADDITIONS, CHROMIUM ALLOYS, CORROSION RESISTANT ALLOYS, ELEMENTS, ENRICHED URANIUM REACTORS, GRAVIMETRIC ANALYSIS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, INDUSTRIAL RADIOGRAPHY, IRON ADDITIONS, IRON ALLOYS, MATERIALS, MATERIALS TESTING, METALS, MICROSCOPY, NONDESTRUCTIVE TESTING, NONMETALS, POWER REACTORS, QUANTITATIVE CHEMICAL ANALYSIS, REACTORS, TESTING, THERMAL ANALYSIS, THERMAL REACTORS, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENTS, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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