第四代核反应堆中超临界二氧化碳腐蚀行为的研究进展  

Research Progress on Corrosion Behavior of Supercritical Carbon Dioxide in Fourth Generation Nuclear Reactors

作　　者：乔爽 余金山 王洪磊 周新贵[1] QIAO Shuang;YU Jinshan;WANG Honglei;ZHOU Xingui(Science and Technology on Advanced Ceramic Fibers and Composites Laboratory,School of Aerospace Science,National University of Defense Technology,ChangSha 410073,China)

机构地区：[1]国防科技大学空天科学学院,新型陶瓷纤维及其复合材料重点实验室,长沙410073

出　　处：《材料研究与应用》2022年第3期460-470,共11页Materials Research and Application

摘　　要：超临界二氧化碳是一种特殊的流体,具有粘度低、扩散系数大、密度大和溶解性较好等特点,因此被认为是第四代核反应堆能量传递的首选材料。由于核反应堆的工作环境十分苛刻,超临界二氧化碳应用于核反应堆系统中易造成材料腐蚀,为确保核反应堆安全有效地运行,对超临界二氧化碳腐蚀行为进行系统研究,介绍了核反应堆的发展历程,重点探讨超临界二氧化碳对合金材料腐蚀的机理,详细阐述了温度、压力、杂质和流速等因素对材料在超临界二氧化碳中腐蚀行为的影响,针对目前的研究提出了亟待解决的问题。Supercritical carbon dioxide is a special fluid with the characteristics of low viscosity,high diffusion coefficient,high density and good solubility.Therefore,it is considered to be the preferred material for energy transfer in fourth generation nuclear reactors.Due to the harsh working environment of nuclear reactors,the application of supercritical carbon dioxide in nuclear reactor system is likely to cause material corrosion.In order to ensure the safe and effective operation of nuclear reactors,the corrosion behavior of supercritical carbon dioxide is systematically studied,and the development history of nuclear reactors is introduced.The corrosion mechanism of carbon dioxide on alloy materials,the effects of temperature,pressure,impurities and flow rate on the corrosion behavior of materials in supercritical carbon dioxide are expounded in detail,and urgent problems to be solved are put forward for the current research.

关 键 词：超临界二氧化碳 材料腐蚀 合金 核反应堆 

分 类 号：TB304[一般工业技术—材料科学与工程]