Research Progress of ODS Steels Corrosion in Heavy Liquid Metal Environment

doi:10.3901/JME.2020.21.001

Abstract

Abstract: Lead-cooled fast reactor (LFR) has been selected as one of the six reactor concepts in the generation IV technology roadmap. The LFR system's enhanced safety and economic performance are of great importance for the choice of a next-generation nuclear system. However,the structural materials of reactor core suffer serious corrosion damage caused by LFR's coolant-heavy liquid metal due to the high density,high flowing rate and high temperature during operation. Oxide dispersion strengthened (ODS) steel,which has excellent irradiation resistance and high temperature mechanical behavior,has been selected as candidate structural material of the advanced fast neutron reactor. The compatibility of ODS steel in contact with heavy liquid metal is one of the key characteristics for the safety of LFR system. The current research progress of ODS steels corrosion in heavy liquid metal environment is reviewed. The factors affecting the corrosion behavior in liquid metal are discussed combined with the oxidation corrosion results in oxidizing gas mixture and supercritical water environment.

Key words: lead-cooled fast reactor, heavy liquid metal, ODS steel, corrosion behavior

CLC Number:

TL341

ZHAO Xi, ZENG Xian, ZHANG Yong, YAN Qingzhi, CHEN Yingxue, YIN Zhenguo. Research Progress of ODS Steels Corrosion in Heavy Liquid Metal Environment[J]. Journal of Mechanical Engineering, 2020, 56(21): 1-10.

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