铅基快堆关键热工水力问题研究综述

Research Progress in Key Thermal-hydraulic Issue of Lead-based Fast Reactor

  • 摘要: 铅基快堆是一种极具发展潜力的第4代核能系统,在燃料增殖和嬗变方面具有独特优势,具有良好的非能动安全特性和经济性,且有利于实现小型化,是目前国际核能领域研究的热点。本文总结了国内外主要铅基堆型,指出了小型化是铅基快堆的发展方向,同时也指出了当前铅基快堆发展所面临的主要问题。针对热工水力关键问题的5个方面,即液态铅/铅铋流动换热特性研究、堆芯/组件热工水力分析、铅池内流动换热现象研究、系统热工水力安全分析以及特殊现象的热工水力分析,对国内外研究现状展开了分析,总结了当前研究成果,并分析了研究的发展趋势以及遇到的技术瓶颈。本文可为铅基快堆的设计和热工水力分析提供一定的建议和指导。

     

    Abstract: Lead-based fast reactor (LFR) is one of the most promising types among the Gen Ⅳ nuclear reactors. It has better transmutation and breeding capability, as well as higher passive safety and economical efficiency, and it is easy to be miniaturized. As a result, LFR becomes a major concern in the nuclear industry. In this paper, the main concepts of LFR were concluded. A research tendency on small modular LFR was indicated and the existing challenges were pointed out. There are mainly 5 key thermal hydraulic issues of LFR, namely the flow dynamics and heat transfer of the coolant, thermal-hydraulic phenomena in reactor core and lead pool, system safety characteristics and some specific thermal-hydraulic phenomena of LFR. The research progress in these 5 issues was analyzed and the current research findings were concluded. Besides, the research tendency and difficulties in each research direction were suggested. This paper can provide useful information for LFR design and thermal-hydraulic analysis.

     

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