小型模块式轻水堆燃料组件临界热流密度研究进展  

Research Progress on Critical Heat Flux of Fuel Assemblies in Small Modular Reactors

作　　者：解衡 朱淦 XIE Heng;ZHU Gan(Institute of Nuclear and New Energy Technology,Collaborative Innovation Center of Advanced Nuclear Energy Technology,Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education,Tsinghua University,Beijing 100084,China)

机构地区：[1]清华大学核能与新能源技术研究院,先进核能技术协同创新中心,先进反应堆工程与安全教育部重点实验室,北京100084

出　　处：《原子能科学技术》2024年第S02期320-331,共12页Atomic Energy Science and Technology

摘　　要：小型模块化反应堆(SMR)在“双碳”大背景下具有广阔的应用前景,对实现能源低碳化转型和能源技术变革等方面具有重要意义。它与常规轻水堆(压水堆和沸水堆)相比堆芯设计差异大,主要表现在小型堆运行功率低、压力低、流速低、堆芯高度低以及功率分布更畸形等,从而导致水冷SMR燃料组件临界热流密度(CHF)研究面临更多难点和挑战。本文综述了CHF机理模型研究、经验关系式研究、子通道分析程序开发等三个方面的发展现状,分析了小型模块式轻水堆CHF研究的特点和难点,并以清华大学研发的一体化全功率自然循环小型压水堆NHR200-Ⅱ为例,介绍了其临界热流密度分析的关键方法研究。Small modular reactors(SMRs)hold significant potential for application in the context of‘dual carbon’and are important for achieving a low-carbon energy transformation and revolutionizing energy technology.Compared to conventional light water reactors(PWRs and BWRs),SMRs exhibit significant differences in core design,primarily characterized by lower operating power,lower pressure,lower flow velocity,lower core height,and more irregular power distribution.These factors introduce additional challenges and complexities in the study of the critical heat flux(CHF)mechanism for SMR fuel assemblies.In this paper,the development of CHF mechanism model,empirical relationship and subchannel analysis program were reviewed.The characteristics and difficulties of small modular light water reactor CHF research were analyzed.Taking NHR200-Ⅱ,an integrated full power natural circulation small pressurized water reactor developed by Tsinghua University as an example,the key methods of critical heat flux analysis were introduced.

关 键 词：小型模块化反应堆 NHR200-Ⅱ燃料组件 临界热流密度试验设计准则 临界热流密度预测方法 临界热流密度机理 

分 类 号：TL33[核科学技术—核技术及应用]