铅冷快堆研究概述
Summary of Lead-Cooled Fast Reactor Research
摘要: 铅冷快堆是指采用液态铅或铅铋合金冷却的快中子反应堆。作为第四代反应堆六种主要堆型之一，铅冷快堆能很好地满足第四代反应堆安全性、经济性、持续性和核不扩散的目标要求。第四代核能系统国际论坛铅冷快堆系统指导委员会选择欧洲铅冷系统ELSY、俄罗斯中型铅冷快堆BREST-OD-300、美国小型自然循环铅冷快堆SSTAR作为铅冷快堆主要参考堆型。文章主要总结了铅冷快堆发展的历史背景和研究现状，并对三个主要参考堆型进行了相关介绍，最后对铅冷快堆发展所面临的挑战进行讨论。
Abstract: Lead-cooled fast reactor is a fast neutron reactor cooled by liquid lead or lead bismuth alloy. As one of the six main reactors of the fourth generation reactor system, lead-cooled fast reactor can well meet the requirements of the fourth generation reactor about safety, economy, sustainability and nuclear non-proliferation. The lead-cooled fast reactor system steering committee of the fourth generation international forum identified the European lead-cooled fast reactor ELSY, the Russian medium-sized lead-cooled fast reactor BREST-OD-300 and the SSTAR system concept designed in the US as the main reference reactor types of the lead-cooled fast reactor. In this paper, the historical background of the development of the lead-cooled fast reactor is summarized, and the current status is introduced. Then, three main reference types are summarized, and finally, the challenges of the lead-cooled fast reactor are put forward.
文章引用：韩金盛, 刘滨, 李文强. 铅冷快堆研究概述[J]. 核科学与技术, 2018, 6(3): 87-97. https://doi.org/10.12677/NST.2018.63011

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