钠冷快堆关键热工水力问题研究现状及展望  

Research Progress in Key Thermal-hydraulic Issue of Sodium-cooled Fast Reactor

作　　者：杨红义[1] 薛秀丽[1] 周志伟[1] 林超[1] 李虹锐 高鑫钊 余新太 马晓[1] 肖宇白 罗锐[2] YANG Hongyi;XUE Xiuli;ZHOU Zhiwei;LIN Chao;LI Hongrui;GAO Xinzhao;YU Xintai;MA Xiao;XIAO Yubai;LUO Rui(China Institute of Atomic Energy,Beijing 102413,China;Tsinghua University,Beijing 100084,China)

机构地区：[1]中国原子能科学研究院,北京102413 [2]清华大学,北京100084

出　　处：《原子能科学技术》2024年第9期1797-1816,共20页Atomic Energy Science and Technology

摘　　要：钠冷快堆因其高热效率、高燃料利用率和固有安全性,以及能够实现闭式燃料循环以减少长寿命放射性废物的独特优势,被认为是第四代核能系统的首选堆型,也是目前国际核能领域的研究热点。本文概述了国际钠冷快堆及热工水力领域的发展历程和未来方向,并指出了当前钠冷快堆热工水力领域发展所面临的主要问题。结合我国的发展现状和挑战,本文针对热工水力研究领域的三个关键核心方面进行了深入分析:冷却剂钠的流动换热特性、堆芯热工水力分析方法,以及自然循环余热排出的设计与验证。总结了国际范围内的研究成果,分析了遇到的技术挑战和未来研究的发展趋势,并探讨了我国在这些领域的研究现状及未来的研究方向。这些分析和总结旨在为中国钠冷快堆技术在提高安全性和经济性方面的技术挑战提供指导,同时也为未来钠冷快堆的热工水力设计和优化提供重要的参考依据,以推动我国钠冷快堆技术的进一步发展。Sodium-cooled fast reactors are considered the preferred reactor type for fourth generation nuclear energy systems due to their high thermal efficiency,high fuel utilization efficiency,inherent safety,and unique advantages of achieving a closed fuel cycle to reduce long-lived radioactive waste.They are also a hot research topic in the international nuclear energy field.An overview of the development history and future directions of sodium-cooled fast reactors and thermal-hydraulic fields on an international scale was provides,and the main problems currently faced in development of sodium-cooled fast reactor thermal-hydraulic fields were pointed out.Based on the current development status and challenges in China,an in-depth analysis of three key core aspects in the field of thermalhydraulic research was conducted,including the flow and heat transfer characteristics of coolant sodium,core thermal-hydraulic analysis methods,and design and capability verification of removing core decay heat through natural circulation.The research achievements on an international scale was summarized,the technological challenges encountered and the future development trends of research were analyzed,and the current research status and future research directions in these fields in China were explored.These analyses and summaries aim to provide guidance for the technical challenges of improving safety and economy in China’s sodium-cooled fast reactor technology,and also provide important reference for the thermal-hydraulic design and optimization of future sodium-cooled fast reactors,in order to promote the further development of China’s sodium-cooled fast reactor technology.

关 键 词：钠冷快堆 热工水力 自然循环 盒间流 固有安全 非能动安全 固有热工流体安全性 湍流模型 

分 类 号：TL33[核科学技术—核技术及应用]