지르코늄합금튜브의 산화와 프레팅마멸 특성
Oxidation and Fretting Wear Characteristics of Zirconium Alloy Tubes
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Oxidation characteristics of Zirlo and Zircaloy-4 tubes, which are widely used as nuclear power fuel cladding, are studied in steam environment up to 1200oC. Oxidation resistances are compared in terms of the mass increase due to the absorption of oxygen. The evolution of microscopic structure accompanied with the oxidation process is investigated. Also, the influence of oxidation on the fretting wear characteristics of the tubes is studied. Piezo-electrically actuated rig is employed to fret the tubes with cross-contacting arrangement. Wear scar is observed and measured, by using microscopes and a 3D-profiler. The results of fretting wear are quantified in terms of scar size, wear volume and wear coefficient, and compared for the three different tube materials of oxidated Zirlo, virgin Zirlo and Zircaloy-4.
Abstract
Oxidation characteristics of Zirlo and Zircaloy-4 tubes, which are widely used as nuclear power fuel cladding, are studied in steam environment up to 1200oC. Oxidation resistances are compared in terms of the mass increase due to the absorption of oxygen. The evolution of microscopic structure accompanied with the oxidation process is investigated. Also, the influence of oxidation on the fretting wear characteristics of the tubes is studied. Piezo-electrically actuated rig is employed to fret the tubes with cross-contacting arrangement. Wear scar is observed and measured, by using microscopes and a 3D-profiler. The results of fretting wear are quantified in terms of scar size, wear volume and wear coefficient, and compared for the three different tube materials of oxidated Zirlo, virgin Zirlo and Zircaloy-4.
참고문헌 (11)
- Pettigrew,M.J, "Flow-induced Vibration: Recent Findings and Open Questions", Nuclear Eng. and Design, 185, pp.249~276 (1998)
- Khushnood,S, "A Review of Heat Exchanger Tube Bundle Vibrations in Two-phase Cross-flow", Nuclear Eng. and Design, 230, pp.233~251 (2004)
- Cho,K.H, "Comparison of Fretting Wear Characteristics of Zircaloy-4 Tube in Light Water and in Air", J. of the KSTLE, 15, pp.83~89 (1999)
- Fisher, N.J, "Fretting-Wear of Zirconium Alloys", Nuclear Eng. and Design, 213, pp.79~90 (2002)
- Park,Y.C, "Influence of Temperature on the Fretting Wear of Advanced Nuclear Fuel Cladding Tube against Supporting Grid", J. of the KSTLE, 22, pp.144~148 (2006)
- Kim,J.S, "Fretting Wear Characteristics of the Corroded Fuel Cladding Tubes for Nuclear Fuel Rod against Supporting Girds", J. of the KSTLE, 23, pp.130~133 (2007)
- Niu,Y, "Phase Stability, Kinetic Diagrams and Diffusion Path in High Temperature Oxidation of Binary Solid-Solution Alloys", J. Mater. Sci. Technol, 19, pp.545~552 (2003)
- Urbanic,V.F, "Zirconium in the Nuclear Industry", ASTM STP, 633, pp.168~ (1977)
- Yau,T.L, "Corrosion of Zirconium and Zirconium Alloys", ASM Handbook, 13, pp.300~324 (2005)
- 정일섭, "인코넬 690 튜브의 상온 프레팅 마멸 특성에 대한 연구", 대한기계학회논문집 A, 33(4), pp.329~336 (2009), 대한기계학회
- Han,J.G, "Zirconium Oxide Formation and Surface Hardening Behavior by Nitrogen Implantation under Oxygen Atmosphere in Zircaloy-4", Surface and Coatings Technology, 97, pp.492~498 (1997)