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添加2 wt%Cu对Zr-4合金显微结构和耐腐蚀性能的影响 被引量:2

EFFECT OF 2 wt%COPPER ADDITION ON MICROSTRUCTURE AND THE CORROSION BEHAVIORS OF ZIRCALOY-4 ALLOY
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摘要 研究了在Zr-4合金中添加2wt%Cu的合金显微组织及其在500℃和10.3 MPa过热蒸汽中的耐腐蚀性能。结果表明,该合金经过热轧、冷轧以及经2 h、580℃真空退火处理后,得到以α-Zr为基体的显微组织,合金中主要存在四方结构的Zr_2Cu和密排六方结构的Zr(Fe,Cr,Cu)_2第二相,Zr_2Cu相有长度1~4μm、厚度约1μm的片状和直径300~500 nm的球形两种形态,并且都会富集一定量的Fe元素。在10.3 MPa、500℃过热水蒸汽中,添加2 wt%Cu的Zr-4合金不发生疖状腐蚀,表明Cu是改善锆合金耐疖状腐蚀性能的有益元素。 The effects of the 2 wt% copper addition on microstructures and the corrosion behaviors of Zirealoy-4 alloys in the 500 °C superheated steam of 10.3 MPa were investigated. The main phase was α-Zr after hot rolled, cold rolled and subsequent vacuum annealing treatment (580 ~C for 2 h). Furthermore, tetragonal-Zr2Cu and hexagonal-Zr ( Fe, Cr, Cn) 2 precipitates were observed by TEM. Enrichment of Fe element was found in lamellar (about 1 -4 μm and 1 μm in length and thickness, respectively) and spherical (300 -500 nm in diameter) Zr2Cu phases. Nodular corrosion was not observed in Zr-4-2Cu after 500 h corrosion in 500 ° C superheated steam of 10.3 MPa, indicating that Cu was beneficial to improving the nodular corrosion resistance of Zircaloy alloy in the environment stated above.
出处 《上海金属》 CAS 北大核心 2012年第4期1-6,共6页 Shanghai Metals
基金 国家自然科学基金项目50871064和50971084 国家先进压水堆重大专项2011ZX06004-023 上海市重点学科建设项目S30107
关键词 Zr_4合金 疖状腐蚀显微组织 Zr-4 Alloys, Cu, Nodular Corrosion, Microstructure
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参考文献12

  • 1Liu Wenqing , Li Qiang , Zhou Bang xin, et al. Effect of heat treatment on the microstructure and corrosion resistance of a Zr-Sn- Nb-Fe-Cr alloy[J]. J Nucl Mater, 2005, 341(2-3): 97-102.
  • 2李强,周邦新,姚美意,刘文庆,褚于良.锆合金在550℃,25MPa超临界水中的腐蚀行为[J].稀有金属材料与工程,2007,36(8):1358-1361. 被引量:13
  • 3卡恩RW,哈森P,克雷默EJ.核应用中的锆合金[M].材料科学与技术丛书,核材料,10B卷,科学出版社,1999:1-45.
  • 4Chakravartty J K. Characterization of hot deformation behaviour of Zr-2. 5Nb-0.5Cu using processing maps [ J ]. J. Nucl. Mater. , 1995, 218 (2) : 247-255.
  • 5Castaldelli L, Fizzotti C. Long-term test results of promising new zirconium alloys[ C ]//Zirconium in the Nuclear Industry: Fifth International Symposium, ASTM STP 754, 1982 : 105- 126.
  • 6Yilmazbayhan A, Motta A T. Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate [ J ]. J. Nucl. Mater., 2004, 324(1): 6-22.
  • 7Hong H S, Moon J S. Investigation on the oxidation characteristics of copper-added modified Zircaloy-4 alloys in pressurized water at 360℃ [J]. J. Nucl. Mater. , 2001, 297 (2) : 113-119.
  • 8Hong H S, Kim H S, Kim S J , et al. Effects of copper addition on the tensile properties and microstructures of modified Zircaloy-4[J]. J. Nucl. Mater., 2000, 280(2) : 230-234.
  • 9Ch Arquetd, Hahnr, Ortlibe, et al. Solubility limits and formation of intermetallic precipitates in Zr-Sn-Fe-Cr alloys [C]//van SWAMLFP, EUCKEN C M. Zirconium in the Nuclear Industry, Eighth International Symposium, ASTM STP 1023. Philadelphia, PA: ASTM, 1989: 405-422.
  • 10周邦新,苗志,李聪.Zr(Fe,Cr)_2金属间化合物在500℃过热蒸汽中的腐蚀研究[J].核动力工程,1997,18(1):53-60. 被引量:4

二级参考文献27

  • 1周邦新,李聪,黄德诚.Zr(Fe,Cr)_2金属间化合物的氧化[J].核动力工程,1993,14(2):149-153. 被引量:14
  • 2周邦新,赵文金,苗志,潘淑芳,李聪,蒋有荣.改善锆-4合金耐腐蚀性能的研究[J].核科学与工程,1995,15(3):242-249. 被引量:25
  • 3雷鸣,刘文庆,严青松,李强,姚美意,周邦新.变形及热处理对Zr-Sn-Nb新锆合金第二相粒子的影响[J].稀有金属材料与工程,2007,36(3):467-470. 被引量:16
  • 4Garzarolli F, Seidel H, Tricot R, Gros J P. In: Eucken C M, Garde A M, eds., Zirconium in the Nuclear Indus- try: Ninth International Symposium, ASTM STP 1132, Philadelphia: American Society for Testing and Materi- als, 1991:395.
  • 5Takeda K, Anada H. In: Sabol G P, Moan G D, eds., Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, West Conshohocken, PA: American Society for Testing and Materials, 2000:592.
  • 6Bouvier P, Godlewski J, Lucazeau G. J Nucl Mater, 2002; 300:118.
  • 7Jeong Y H, Kim H G, Kim T H. J Nucl Mater, 2003; 317: 1.
  • 8Sabol G P. J ASTM Int, 2005; 2:3.
  • 9Bossis F, Pecheur D, Hanifi K, Thomazet J, Blat M. J ASTM Int, 2006; 3:494.
  • 10Kim H G, Jeong Y H, Kim T H. J Nucl Mater, 2004; 326: 125.

共引文献21

同被引文献28

  • 1薛祥义,白新德,田振业,周青山,刘建章.锆合金疖状腐蚀研究综述[J].稀有金属材料与工程,2004,33(9):902-906. 被引量:17
  • 2周邦新,姚美意,李强,夏爽,刘文庆,褚于良.Zr-Sn-Nb合金耐疖状腐蚀性能的研究[J].稀有金属材料与工程,2007,36(8):1317-1321. 被引量:22
  • 3姚美意,周邦新,李强,刘文庆,王树安,黄新树.第二相对Zr-4合金在400℃过热蒸汽中腐蚀吸氢行为的影响[J].稀有金属材料与工程,2007,36(11):1915-1919. 被引量:16
  • 4李中奎,周军.2008年锆行业大会论文集[C].北京:冶金工业出版社.2008.
  • 5Sawarn,Tapan K,Banerjee,Suparna,Samanta,Akanksha,Rath B N,Kumar Sunil.Study of oxide andα-Zr(O)growth kinetics from high temperature steam oxidation of Zircaloy-4 cladding[J].Journal of Nuclear Materials,2015,467(11):820.
  • 6Cockeram B V,Hollenbeck J L.The role of stressstate on the deformation and fracture mechanism of hydrided and non-hydrided Zircaloy-4[J].Journal of Nuclear Materials,2015,467(11):9.
  • 7Hyun Ju Jin,Tae Kyu Kim.Neutron irradiation performance of Zircaloy-4 under research reactor operating conditions[J].Annals of Nuclear Energy,2015,75(1):309.
  • 8Ahmad M,Akhter J I,Shaikh M A,Akhtar M,Iqbal M,Chaudhry M A.Hardness and microstructural studies of electron beam welded joints of Zircaloy-4 and stainless steel[J].Journal of Nuclear Materials,2002,301(2):118.
  • 9Paolo Ferro,Andrea Zambon,Franco Bonoke.Investigation of electron-beam welding in wrought Inconel 706-experimental and numerical analysis[J].Materials Science and Engineering,2005.94.
  • 10Goldak J,Chakravarti A,Bibby M.A new finite element model for welding heat sources[J].Metallurgical Transactions B,1984,15(2):299.

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