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铅冷快堆结构材料耐蚀涂层技术研究概述

Overview of Corrosion-resistant Coating Technology for Lead-cooled Fast Reactor Structure Materials
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摘要 铅冷快堆是采用液态铅或铅铋合金冷却的快中子反应堆。作为第四代反应堆六种主要堆型之一,铅冷堆具有高负荷跟踪、高固有安全性、高功率密度和长换料周期等特点,因此铅冷快堆很好地满足了第四代反应堆安全性、经济性、持续性和核不扩散的目标要求。但铅或铅铋合金对结构材料具有很强的腐蚀性,必须采用复杂的氧控技术或优良的耐蚀材料才能保证反应堆长期安全运行。国内外采用了硅增强耐热钢(如俄罗斯燃料包壳用EP823(16Cr12MoWSiVNbMn)、蒸汽发生器用EP302M(10Cr15Ni9Si3Nb))、铝增强铁马钢和涂层制备技术来解决液态铅/铅铋对结构材料的腐蚀问题。本文主要总结了铅冷快堆结构材料典型耐蚀涂层技术的研究现状,并对耐蚀涂层的发展前景进行了展望。 Lead-cooled fast reactor is a fast neutron reactor cooled using liquid lead or lead-bismuth alloy.As one of the six main reactors of fourth-gene-ration,lead cooling reactor has the characters of high load tracking,high inherent safety,high power density and long feeding cycle.It meets the requirements of safety,economy,sustainability and nuclear nonproliferation of the fourth-generation reactors.However,lead or lead bismuth alloy are corrosive media for structural material,so complex oxygen control technology or excellent corrosion-resistant materials must be used to ensure the long-term safe operation of the reactor.At present,silicon-reinforced heat-resistant steel,for example Russian cladding materials of EP823(16Cr12MoWSiVNbMn),steam generator materials of EP302M(10Cr15Ni9Si3Nb),aluminum reinforced ferrite martenite steel and coating preparation technology are used to solve the corrosion problem of liquid lead/lead/bismuth on structural materials.The paper mainly summarizes the research status of typical corrosion-resistant coating technology,and describes the coating prospects in the future.
作者 梁娜 姚存峰 龙斌 付晓刚 LIANG Na;YAO Cunfeng;LONG Bin;FU Xiaogang(China Institute of Atomic Energy,Beijing 102413,China;Institute of Modern Physics,Lanzhou 730000,China)
出处 《材料导报》 EI CAS CSCD 北大核心 2022年第23期93-99,共7页 Materials Reports
关键词 铅铋冷却 结构材料 氧化 耐蚀涂层 lead-bismuth cooling structure material oxidation corrosion-resistant coating
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