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铅基快堆关键热工水力问题研究综述

  • Xi'an Jiaotong University

科研成果: 期刊稿件文献综述同行评审

27 引用 (Scopus)

摘要

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.

投稿的翻译标题Research Progress in Key Thermal-hydraulic Issue of Lead-based Fast Reactor
源语言繁体中文
页(从-至)326-336
页数11
期刊Yuanzineng Kexue Jishu/Atomic Energy Science and Technology
53
2
DOI
出版状态已出版 - 20 2月 2019

关键词

  • Lead-based fast reactor
  • Research review
  • Thermal-hydraulics

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