铅冷快堆材料腐蚀研究与防护方法  

Study and Protection Methods for Corrosion of the Lead-based on Fast Reactor Materials

作　　者：魏珂 张添翼 黄东兴 WEI Ke;ZHANG Tianyi;HUANG Dongxing(Nuclear Technology Support Center,State Administration of Science,Technology and Industry for National Defense,Beijing 100071,China)

机构地区：[1]国防科技工业局核技术支持中心,北京100071

出　　处：《核科学与工程》2024年第6期1419-1426,共8页Nuclear Science and Engineering

摘　　要：铅冷快堆是第四代核能系统的新型反应堆之一,能够提高反应堆核燃料利用效率、减少放射性废物产生、提高固有安全性。材料腐蚀问题一直是限制铅冷快堆发展的主要因素,随着腐蚀机理与材料试验研究的深入,提高材料耐腐蚀能力的方法也得到了巨大发展。控制铅铋冷却剂的含氧量、在材料表面包覆耐蚀涂层是目前主要的提高材料耐腐蚀能力的方法。本文分析了材料腐蚀机理与防护方法的研究进展,为材料在铅基核能系统的应用提供了参考。Lead-cooled fast reactor is one of the new types of reactors in the fourth-generation nuclear power system,which can increase nuclear fuel utilization efficiency,reduce generation of radioactive wastes,and improve the inherent safety.The issue of material corrosion has always been the main factor limiting the development of lead-cooled fast reactors.With the deepening of study on corrosion mechanisms and material experiment,methods to improve the corrosion resistance of materials have also been greatly developed.Controlling the oxygen content of lead-bismuth coolant,and coating the material surface with corrosion-resistant coatings are currently the main corrosion resistance methods.This article analyzes the study progress of material corrosion mechanism and protection methods,providing reference for the application of materials in lead-based nuclear energy systems.

关 键 词：铅冷快堆 腐蚀防护 氧控技术 涂层 

分 类 号：TB37[一般工业技术—材料科学与工程]