铅冷能源系统中液态金属与铁基合金相容性的研究进展

doi:10.11896/cldb.19010064

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Abstract Nuclear power is a kind of clean energy which can effectively solve the energy and environmental problems and has been widely developed in the world. Commercial reactors include the GenerationⅡ and Generation Ⅲ thermal neutron reactors, which have problems such as low utilization rate of uranium resources, continuous accumulation of radioactive waste and potential nuclear safety. The Generation Ⅳ energy system with higher safety and economy becomes a research hot-spot. The lead-cooled fast reactor using lead or lead-based alloys as the main coolant is considered to be one of the most promising Generation Ⅳ reactors, as liquid lead and its alloys have excellent thermal and nuclear physical pro-perties. Liquid lead is also used as target material and coolant in the accelerator driven sub-critical system and considered to be one of the most promising energy exchange media for solar thermal systems.
　　Lead based coolant has high melting point and can operate at rather high temperature. It has obvious advantages in power generation efficiency, while the harsh service environment, such as high operation temperature, strong irradiation intensity, requires new grade high performance structural materials. Especially, most of alloys in liquid lead will suffer to significant corrosion problems due to the selective dissolution of alloying elements. The compatibility of structural materials with liquid lead is a main bottleneck for the engineering application of lead cooled energy systems. Corrosion in the lead-based coolant, includes dissolution of materials, transport between solid and liquid phases and reaction between corrosion products and impurities, which is a complex process. The factors influencing corrosion behavior include the material feature and external factors, such as the type of materials, microstructure, chemical composition and surface state, as well as the type of coolant, temperature, oxygen concentration, flow rate and corrosion time. The research on the compatibility between structural materials and liquid metals becomes the key issue for the engineering application of lead cooled energy systems.
　　In this paper, the main problem of restricting the development of structural materials for lead-cooled energy systems is summarized, focused on the relationship between material composition and microstructure characteristics and their dissolution and oxidation behavior in liquid lead. The progress of the development of metal and non-metallic corrosion inhibitors; the compatibility between stainless steel and liquid lead, especially, the development of oxide dispersion strengthened (ODS) steels, alumina formed austenitic (AFA) steels and FeCrAl alloys application for liquid lead cooled systems are summarized and prospected. The factors affecting corrosion behavior and the related mechanism are also summarized, and the effect and movement mode of typical elements on the oxide layer during the corrosion process are analyzed, which provides a reference for the development of key structural materials promising for application in lead cooled energy systems.

Key words： lead cooled dissolution and oxidation oxide dispersion strengthened steels alumina-forming austenitic steel FeCrAl alloys corrosion resistance

Published: 16 January 2020

CLC number:

TG17

About author:: Lingzhi Chenreceived her Master of Science Degree in chemistry from University of Science and Technology Beijing in 2011. She is currently pursuing her Ph.D. in the same university under the supervision of Prof. Zhangjian Zhou. Her main research area focus on the preparation of ODS steel and compatibility of iron-based alloys with liquid lead-based alloys;Zhangjian Zhouis currently a full professor in University of Science and Technology Beijing. He received M.E. degree in mineralogy from China Geoscience University, in 1996, and received Ph.D. degree in materials science from University of Science and Technology Beijing in 2007. He is a member of the advisory editorial board of the Journal of Nuclear Materials and member of international advisory committees for FGM’S. His recent research interest is the design, synthesis and investigation of advanced materials application for the extreme environment, such as nuclear system.

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	CHEN Lingzhi
	ZHOU Zhangjian
	Carsten Schroer

Cite this article:

CHEN Lingzhi,ZHOU Zhangjian,Carsten Schroer. Research Progress on Compatibility of Liquid Metal and Iron-based Alloy in Lead Cooled Energy Systems[J]. Materials Reports, 2020, 34(5): 5096-5101.

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http://www.mater-rep.com/EN/10.11896/cldb.19010064 OR http://www.mater-rep.com/EN/Y2020/V34/I5/5096

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