| [1] Motta A T, Yilmazbayhan A, Marcelo J, et al. Zirconium alloys for supercritical water reactor applications: challenges and possibilities [J]. J Nucl Mater, 2007, 371(1/2/3): 61-75.[2] Cox B. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys [J]. J Nucl Mater, 2005, 336(2/3): 331-368.[3] Rez P, Alvarez J R. Calculation of cohesion and changes in electronic structure due to impurity segregation at boundaries in iron [J]. Acta Mater, 1999, 47(15): 4069-4075.[4] Bika D, McMahon J. A model for dynamic embrittlement [J]. Acta Metall, 1995, 43(5): 1909-1916.[5] Heuer J K, Okamoto P R, Lam N Q, et al. Disorder-induced melting in nickel: implication to inter granular sulfur embrittlement [J]. J Nucl Mater, 2002, 301(2/3): 129-141.[6] Charquet D, Senevat J, Marcon J P. Influence of sulfur content on the thermal creep of zirconium alloy tubes at 400 C [J]. J Nucl Mater, 1998, 255(1): 78-82.[7] Charquet D. Phase constitution and steam corrosion resistance of binary Zr-S alloys [J]. J Nucl Mater, 2002, 304(2/3): 246-248.[8] 陈燕鹏, 姚美意, 黄娇, 等. 微量硫对Zr-4 合金在360 C LiOH 水溶液中耐腐蚀性能的影响[J]. 腐蚀与防护, 2014, 35(2): 107-111.[9] 周邦新, 李强, 姚美意, 等. 锆-4合金在高压釜中腐蚀时氧化膜显微组织的演化[J]. 核动力工程, 2005, 26(4): 364-371.[10] Stojilovic N, Bender E T. High-temperature auger electron spectroscopy of zircaloy-4 [J]. Appl Surf Sci, 2005, 252: 1806-1811.[11] 徐启迪, 黄娇, 姚美意, 等. 添加S对Zr-Sn-Nb-Fe锆合金中第二相的影响[J]. 稀有金属材料与工程, 2015, 44(1): 107-111.[12] Grabke H J, Wiemer D. Segregation of sulfur during growth of oxide scales [J]. Appl Surf Sci, 1991, 47(3): 243-250.[13] Jeong Y H, Lee K O, Kim H G. Correlation between microstructure and corrosion behavior of Zr-Nb binary alloy [J]. J Nucl Mater, 2002, 302(1): 9-19.[14] Kim H G, Jeong Y H, Kim T H. Effect of isothermal annealing on the corrosion behavior of Zr-xNb alloys [J]. J Nucl Mater, 2004, 326(2): 125-131.[15] Omstock R J, Sabol G P, Schoenberger G, et al. Influence of processing variables and alloy chemistry on the corrosion behavior of ZIRLO nuclear fuel cladding [C]// Zirconium in theNuclear Industry: 11th International Symposium. 1996: 710-725.[16] Rudling P, Wikmark G. A unified model of zircaloy BWR corrosion and hydriding mechanisms [J]. J Nucl Mater, 1999, 265(1): 44-59.[17] Rudling P, Wikmark G, Lehtinen B, et al. Impact of second phase particles on BWR Zr-2 corrosion and hydriding performance [C]// Zirconium in Nuclear Industry: 12th InternationalSymposium. 2000: 678-706.[18] Smeggil J G, Funkenbusch A W, Bornstein N S. A relationship between indigenous impurity elements and protective oxide scale adherence characteristics [J]. Metall Mat Trans A, 1986, 17(6): 923-932.[19] Lees D G. On the reasons for the effects of dispersions of stable oxides and additions of reactive elements on the adhesion and growth-mechanisms of chromia and alumina scales-the “sulfur effect” [J]. Oxid Met, 1987, 27: 75-81.[20] McDonald J E, Eberhart J G. Institute of metals division-adhesion in aluminum oxide-metal systems [J]. Trans TMS-AIME, 1965, 233: 512-517.[21] 周邦新, 李强, 刘文庆, 等. 水化学及合金成分对锆合金腐蚀时氧化膜显微组织演化的影响[J]. 稀有金属材料与工程, 2006, 35(7): 1009-1016.[22] Zhou B X, Li Q, Yao M Y, et al. Effect of water chemistry and composition on microstructural evolution of oxide on Zr alloys [C]// Zirconium in the Nuclaer Industry: 15th InternationalSymposium. 2009: 360-380.[23] 李士炉. 添加Nb或Cu对锆合金在500 C过热蒸汽中耐腐蚀性能的影响[D]. 上海: 上海大学, 2011：53.[24] 刘文庆, 朱晓勇, 王晓姣, 等. Nb元素和Fe元素对锆合金耐腐蚀性能的影响[J]. 原子能科学技术, 2010, 44(12): 1477-1481. |
