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High-temperature Oxidation Behavior of Zircaloy-4 and Zirlo in Steam Ambient 被引量:8

High-temperature Oxidation Behavior of Zircaloy-4 and Zirlo in Steam Ambient
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摘要 The oxidation characteristics for Zircaloy-4 and Zirlo in the temperature range of 700-1200°C under steam supply condition were investigated by using a modified thermo-gravimetric analyzer.The specimens were oxidized for 3600 s at each temperature and then quenched in a furnace.The oxidation rate constants were measured from the weight gains to evaluate the oxidation behavior in Zircaloy-4 and Zirlo.The weight gain rates of Zirlo were lower than those of Zircaloy-4,leading to the low rate constants.The different oxidation behaviors between both cladding materials were considered to be due to the difference in their chemical compositions. The oxidation characteristics for Zircaloy-4 and Zirlo in the temperature range of 700-1200°C under steam supply condition were investigated by using a modified thermo-gravimetric analyzer.The specimens were oxidized for 3600 s at each temperature and then quenched in a furnace.The oxidation rate constants were measured from the weight gains to evaluate the oxidation behavior in Zircaloy-4 and Zirlo.The weight gain rates of Zirlo were lower than those of Zircaloy-4,leading to the low rate constants.The different oxidation behaviors between both cladding materials were considered to be due to the difference in their chemical compositions.
出处 《Journal of Materials Science & Technology》 SCIE EI CAS CSCD 2010年第9期827-832,共6页 材料科学技术(英文版)
基金 supported by the Korea Science & Engineering Foundation through the BAERI Program(GrantNo.M20508110003)
关键词 ZIRCALOY-4 Zirlo OXIDATION Zircaloy-4 Zirlo Oxidation
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  • 1G.P. Sabol, G.R. Kilp, M.G. Balfour and E. Roberts: Development of a Cladding Alloy for High Burnup, in Proc. 8th Int. Syrup. on Zirconium in the Nuclear Industry, ASTM STP, 1989, 1023, 227.
  • 2J.P. Mardon, D. Charquet and J. Senevat: Influence of Composition and Fabrication Process on out-of-pile and in-pile Properties of M5 Alloy, in Zirconium in the Nuclear Industry: Twelfth Symposium, ASTM STP, 2000, 1354, 505.
  • 3V. Nikulina, P.P. Markelov and M. M. Peregud: J. Nucl. Mater., 1996, 238, 205.
  • 4M. Garde: ASTM STP, 1991, 1132, 566.
  • 5T. Isobe and Y. Matsuo: ASTM STP, 1991, 1132, 346.
  • 6Y.H. Jeong, S.Y. Park, M.H. Lee, B.K. Chio, J.H. Baek, J.Y. Park, J.H. Kim and H.G. Ki: J. Nucl. Sci. Technol.. 2006, 43, 977.
  • 7F. Nagase,- T. "Otomo and H. Uetsuka: J. Nucl. Sci. Technol., 2003, 40, 213.
  • 8V.F. Urbanic: ASTM STP, 1977, 633, 168.
  • 9J.H. Baek and Y.H. Jeong: J. Nucl. Mater., 2007, 361, 30.
  • 10USNRC-SRP (Standard Review Plan), Sec. 4.2, NUREG-0800.

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