DOI QR코드

DOI QR Code

지르코늄 합금 튜브의 산화와 프레팅 마멸 특성

Oxidation and Fretting Wear Characteristics of Zirconium Alloy Tubes

  • 정일섭 (영남대학교 기계공학부) ;
  • 이호성 (경북대학교 신소재공학부) ;
  • 이명호 (영남대학교 기계공학부)
  • Chung, Il-Sup (School of Mechanical Engineering, Yeungnam University) ;
  • Lee, Ho-Seong (Materials Science and Metallurgical Engineering, Kyungpook University) ;
  • Lee, Myung-Ho (School of Mechanical Engineering, Yeungnam University)
  • 발행 : 2009.08.31

초록

Oxidation characteristics of Zirlo and Zircaloy-4 tubes, which are widely used as nuclear power fuel cladding, are studied in steam environment up to $1200^{\circ}C$. 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.

키워드

참고문헌

  1. Pettigrew,M.J., Taylor,C.E., Fisher,N.J., Yetisir,M., and Smith,B.A.W., 'Flow-induced Vibration: Recent Findings and Open Questions', Nuc/ear Eng. and Design, Vol. 185, pp. 249-276, 1998 https://doi.org/10.1016/S0029-5493(98)00238-6
  2. Khushnood,S., Khan,Z.M., Malik,M.A., Koreshi, Z.,u., and Khan,M.A., 'A Review of Heat Exchanger Tube Bundle Vibrations in Two-phase Cross-flow', Nuc/ear Eng. and Design, Vol. 230, pp. 233-251, 2004 https://doi.org/10.1016/j.nucengdes.2003.11.024
  3. Cho,K.H. and Kim,S.S., 'Comparison of Fretting Wear Characteristics of Zircaloy-4 Tube in Light Water and in Air', J. of the KSTLE, Vol. 15, pp. 83-89, 1999
  4. Fisher, N.J, Weckwerth, M.K. and Grandison, D.A.E., 'Fretting-Wear of Zirconium Alloys', Nuclear Eng. and Design, Vol. 213, pp. 79-90, 2002 https://doi.org/10.1016/S0029-5493(02)00035-3
  5. Park,Y.C., Jeong,S.H., Kim,J.S., Kim,Y.H. and Lee, Y.Z., 'Influence of Temperature on the Fretting Wear of Advanced Nuclear Fuel Cladding Tube against Supporting Grid', J. of the KSTLE, Vol 22, pp. 144-148, 2006
  6. Kim,J. S., Park,S.M., Kim,Y.H., Lee,S.J. and Lee, Y.Z., 'Fretting Wear Characteristics of the Corroded Fuel Cladding Tubes for Nuclear Fuel Rod against Supporting Girds', J. of the KSTLE, Vol. 23, pp. 130-133, 2007
  7. Niu,Y. and Gesmundo,F., 'Phase Stability, Kinetic Diagrams and Diffusion Path in High Temperature Oxidation of Binary Solid-Solution Alloys', J. Mater. Sci. Technol., Vol. 19, pp. 545-552, 2003
  8. Urbanic,Y.F., 'Zirconium in the Nuclear Industry', ASTM STP, 633, p.168, 1977
  9. Yau,T.L., Sutherlin,R.C. and Chang,A.W., 'Corrosion of Zirconium and Zirconium Alloys', ASM Handbook, Vol. 13B, pp. 300-324, 2005
  10. Chung,I., Lee,M. and Chai,Y., 'Fretting Wear Characteristics of Inconel 690 Tubes in Room Temp-erature', Trans. of the KSME, Vol. 33, pp. 329-336, 2009
  11. Han,J.G, Lee,J.S., Kim,W., Sun,D.S. and Chung,K. H., 'Zirconium Oxide Formation and Surface Hardening Behavior by Nitrogen Implantation under Oxygen Atrnosphere in Zircaloy-4', Surface and Coatings Technology, Vol. 97, pp. 492-498, 1997 https://doi.org/10.1016/S0257-8972(97)00162-X