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作 者:刘蔚伟[1] 杨鸿 姜峨[1] 黄彦平[2] 张根 龚宾[1] 赵永福[1] 马韦刚[1] LIU Weiwei;YANG Hong;JIANG E;HUANG Yanping;ZHANG Gen;GONG Bin;ZHAO Yongfu;MA Weigang(Reactor Engineering Sub-Institute,Nuclear Power Institute of China,Chengdu 610213,China;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China,Chengdu 610213,China)
机构地区:[1]中国核动力研究设计院反应堆工程研究所,四川成都610213 [2]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,四川成都610213
出 处:《原子能科学技术》2021年第S02期242-248,共7页Atomic Energy Science and Technology
基 金:中核集团“青年英才”项目。
摘 要:本文研究了4种超临界二氧化碳核能动力转换系统关键高温部件候选材料在650℃、20 MPa超临界二氧化碳环境中的均匀腐蚀行为,利用扫描电子显微镜、X射线能谱仪、X射线衍射仪和辉光放电光谱仪分析了氧化膜微观形貌、组织结构和成分分布。结果表明:奥氏体不锈钢310S及316NG、铁镍基合金Incoloy-800H、镍基合金Inconel-625三类材料在650℃、20 MPa的超临界二氧化碳环境中均表现出良好的耐腐蚀性能,腐蚀动力学遵循抛物线规律;Cr、Ni含量的增加可提高材料耐腐蚀性能,310S、Incoloy-800H和Inconel-625耐腐蚀性能优于316NG;310S和316NG在超临界二氧化碳环境中存在渗碳行为,材料渗碳现象可能会加速材料的腐蚀并影响其力学性能。本研究评价了不同候选材料与超临界二氧化碳的相容性,为超临界二氧化碳核能动力转换系统关键部件材料性能的评估及应用提供了关键性实验数据支撑。The general corrosion behavior of four candidate materials for key high-temperature components of supercritical carbon dioxide nuclear power conversion system was studied in 650℃/20 MPa supercritical carbon dioxide.Morphologies,microstructures and chemical compositions of oxide films were analyzed by scanning electron microscope,energy dispersive spectroscopy,X-ray diffraction and glow discharge optical emission spectroscopy.The results show that austenitic stainless steel 310S and 316NG,iron nickel base alloy Incoloy-800H and nickel base alloy Inconel-625 have good corrosion resistance in 650℃/20 MPa supercritical carbon dioxide and the corrosion kinetics follows parabolic law.The increase of Cr and Ni contents can enhance the corrosion resistance of the materials and 310S,Incoloy-800H and Inconel-625 have better corrosion resistance than 316NG.310S and 316NG have carburizing behavior in supercritical carbon dioxide.Carburizing may accelerate the corrosion of materials and affect their mechanical properties.This study evaluates the compatibility of different candidate materials in supercritical carbon dioxide,which provides the key experimental data support for the material evaluation of the critical components of the supercritical carbon dioxide nuclear power conversion system.
分 类 号:TL341[核科学技术—核技术及应用]
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