锆基耐事故燃料包壳保护涂层研究进展

E. Kashkarov, B. Afornu, D. Sidelev, M. Krinitcyn, Veronica Gouws, A. Lider
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引用次数: 47

摘要

锆基合金由于其可用于轻水堆堆芯的性能,已经为核工业服务了几十年。然而,轻水堆的严重事故指导了事故容忍燃料(ATF)概念的研究和发展,旨在提高核燃料在正常运行、运行瞬态和可能的事故情景下的安全性。本文介绍了Zr合金ATF包层防护涂层的最新研究进展,包括Zr合金在轻水堆正常工况和事故工况下的性能。对涂层包层的保护和氧化机理以及涂层与锆合金之间的相互扩散进行了研究。概述了阻隔涂层的最新发展,并提出了抑制相互扩散的可能的阻隔层和结构设计。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings
Zirconium-based alloys have served the nuclear industry for several decades due to their acceptable properties for nuclear cores of light water reactors (LWRs). However, severe accidents in LWRs have directed research and development of accident tolerant fuel (ATF) concepts that aim to improve nuclear fuel safety during normal operation, operational transients and possible accident scenarios. This review introduces the latest results in the development of protective coatings for ATF claddings based on Zr alloys, involving their behavior under normal and accident conditions in LWRs. Great attention has been paid to the protection and oxidation mechanisms of coated claddings, as well as to the mutual interdiffusion between coatings and zirconium alloys. An overview of recent developments in barrier coatings is introduced, and possible barrier layers and structure designs for suppressing mutual diffusion are proposed.
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