Oxidation Characteristics of Haynes 282 Nickel-Based Alloy in Supercritical Water at 600-700℃
摘 要
在600~700℃、25 MPa超临界水中对Haynes 282镍基合金进行氧化,研究了不同温度和时间下合金的氧化动力学曲线以及氧化膜的表面形貌、微观结构和物相组成等。结果表明:Haynes 282合金的单位面积氧化质量增加随着温度的升高和时间的延长而增大;600℃时合金的氧化动力学曲线遵循抛物线规律,650,700℃时的氧化动力学曲线介于抛物线和直线规律之间;合金表面的氧化膜具有双层结构,外层为呈松散的多面体形状的微米尺寸氧化物颗粒,内层为由细小晶粒组成的致密氧化膜;600℃氧化后氧化膜内层主要为Cr2O3,外层则为TiO2;650℃氧化后氧化膜外层由TiO2与MnCr2O4组成,而内层由Cr2O3和少量的MnCr2O4组成;700℃氧化后氧化膜外层由NiCr2O4与MnCr2O4组成,而内层由Cr2O3和少量的MnCr2O4组成。
Abstract
Haynes 282 nickel-based alloy was oxidized in supercritical water at 600-700℃ and 25 MPa, and then oxidation kinetics curves of the alloy and the surface morphology, microstructure and phase composition of the oxide film were investigated. The results show that the oxidation mass gain per unit area increased with the increase of the temperature and time. The oxidation kinetics curves followed parabolic law at 600℃ while obeyed the law between straight law and parabolic law at 650, 700℃. A double-layered oxide film was formed on the surface of the alloy. The outer layer consisted of scattered oxide particles in micrometer size with the loose polyhedral shape. The inner layer was a compact oxide film composed of tiny grains. The inner layer mainly composed of Cr2O3 and the outer layer composed of TiO2 were formed on the surface of the alloy at 600℃. The outer layer of the oxide film at 650℃ was composed of MnCr2O4 and TiO2, and the inner layer consisted of Cr2O3 and a small amount of MnCr2O4. The outer layer of the oxide film at 700℃ was composed of NiCr2O4 and MnCr2O4, and the inner layer consisted of Cr2O3 and a small amount of MnCr2O4.
中图分类号 TK224 TM621 DOI 10.11973/jxgccl201803001
所属栏目 试验研究
基金项目 国家自然科学基金资助项目(51471069);北京市自然科学基金资助项目(2152029);中央高校基本科研业务费专项资金资助项目(2015ZZD05)
收稿日期 2017/12/10
修改稿日期 2018/1/15
网络出版日期
作者单位点击查看
备注徐鸿(1959-),男,浙江黄岩人,教授,博士
引用该论文: XU Hong,DENG Bo,ZHU Zhongliang,GUO Peng,ZHANG Naiqiang. Oxidation Characteristics of Haynes 282 Nickel-Based Alloy in Supercritical Water at 600-700℃[J]. Materials for mechancial engineering, 2018, 42(3): 1~8
徐鸿,邓博,朱忠亮,郭鹏,张乃强. Haynes 282镍基合金在600~700℃超临界水中的氧化特性[J]. 机械工程材料, 2018, 42(3): 1~8
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参考文献
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【2】张涛, 郝丽婷, 田峰, 等. 700 ℃超超临界火电机组用高温材料研究进展[J]. 机械工程材料, 2016, 40(2): 1-6.
【3】VISWANATHAN R, COLEMAN K, RAO U. Materials for ultra-supercritical coal-fired power plant boilers[J]. International Journal of Pressure Vessels and Piping, 2006, 83(11/12): 778-783.
【4】YAMAGUCHI T. Structure of subcritical and supercritical hydrogen-bonded liquids and solutions[J]. Journal of Molecular Liquids, 1998, 78(1/2): 43-50.
【5】陈石富, 秦鹤勇, 张文云, 等. 700 ℃超超临界锅炉用镍基合金管材的研究进展[J]. 机械工程材料, 2012, 36(11): 1-4.
【6】PIKE L M. Haynes® 282TM alloy: A new wrought superalloy designed for improved creep strength and fabricability[C]//Proceedings of GT2006 ASME Turbo Expo 2006: Power for Land, Sea, and Air. Barcelona: ASME, 2006: 1031-1039.
【7】PIKE L M. Low-cycle fatigue behaviour of Haynes® 282® and other wrought gamma-prime strengthened alloys[C]//Proceedings of GT2007 ASME Turbo Expo 2007: Power for Land, Sea, and Air. Montreal: ASME, 2007: 161-169.
【8】PÉREZ-GONZÁLEZ F A, OCA G M D, COLÁS R. High temperature oxidation of the Haynes 282© nickel-based superalloy[J]. Oxidation of Metals, 2014, 82(3/4): 145-161.
【9】唐丽英, 周荣灿, 侯淑芳, 等. 两种表面状态的Haynes 282在750 ℃高温蒸汽中的氧化行为[J]. 中国电机工程学报, 2016, 36(10): 2728-2733.
【10】李江, 周荣灿, 唐丽英, 等. 模拟燃用高硫煤锅炉烟气环境中Haynes 282合金的腐蚀行为[J]. 热力发电, 2017, 46(10): 30-35.
【11】KIM D, SAH I, LEE H J, et al. Hydrogen effects on oxidation behaviors of Haynes 230 in high temperature steam environments[J]. Solid State Ionics, 2013, 243(4): 1-7.
【12】GORMAND M, HIGGINSON R L, DU H, et al. Microstructural analysis of IN617 and IN625 oxidised in the presence of steam for use in ultra-supercritical power plant[J]. Oxidation of Metals, 2013, 79(5/6): 553-566.
【13】KIM D, KIM D, LEE H J, et al. Corrosion characteristics of Ni-base superalloys in high temperature steam with and without hydrogen[J]. Journal of Nuclear Materials, 2013, 441(1/2/3): 612-622.
【14】CHANG K H, HUANG J H, YAN C B, et al. Corrosion behavior of Alloy 625 in supercritical water environments[J]. Progress in Nuclear Energy, 2012, 57(5): 20-31.
【15】ZHONG X Y, HAN E H, WU X. Corrosion behavior of Alloy 690 in aerated supercritical water[J]. Corrosion Science, 2013, 66(1): 369-379.
【16】ZHANG Q, TANG R, YIN K, et al. Corrosion behavior of Hastelloy C-276 in supercritical water[J]. Corrosion Science, 2009, 51(9): 2092-2097.
【17】ZHANG N Q, ZHU Z L, XU H, et al. Oxidation of ferritic and ferritic-martensitic steels in flowing and static supercritical water[J]. Corrosion Science, 2016, 103: 124-131.
【18】CHANG K H, CHEN S M, YEH T K, et al. Effect of dissolved oxygen content on the oxide structure of Alloy 625 in supercritical water environments at 700 ℃[J]. Corrosion Science, 2014, 81: 21-26.
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【20】LOGNIG R E, SCHMIDT H P, HENNESEN K, et al. Diffusion of cations in chromia layers grown on iron-base alloys[J]. Oxidation of Metals, 1992, 37(1/2): 81-93.
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【22】PAN G Q, WU G H, XIU Z Y, et al. Microstructure, oxidation resistance and high-temperature strength of a new class of 3D open-cell nickel-based foams[J]. Materials Characterization, 2012, 70(4): 125-136.
【23】SENNOUR M, MARCHETTI L, MARTIN F, et al. A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor[J]. Journal of Nuclear Materials, 2010, 402(2/3): 147-156.
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