液态金属快堆分析方法与自主化软件的研发与验证  

Research on High-precision Numerical Analysis Method of Liquid-metal Fast Reactor and Key Software Development

作　　者：吴宏春[1] 郑友琦[1] 曹良志[1] 杜夏楠 王学松[2] 祖铁军[1] 刘宙宇[1] 贺清明[1] 陈荣华[1] 葛莉 杨睿 高鑫钊 王事喜[2] 阿热爱 WU Hongchun;ZHENG Youqi;CAO Liangzhi;DU Xianan;WANG Xuesong;ZU Tiejun;LIU Zhouyu;HE Qingming;CHEN Ronghua;GE Li;YANG Rui;GAO Xinzhao;WANG Shixi;A Reai(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China;China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]西安交通大学核科学与技术学院,陕西西安710049 [2]中国原子能科学研究院,北京102413

出　　处：《原子能科学技术》2025年第4期824-837,共14页Atomic Energy Science and Technology

基　　金：核能开发项目。

摘　　要：液态金属冷却快中子核反应堆(简称液态金属快堆)是我国核能发展“三步走”战略中承上启下的关键环节。高精度的液态金属快堆数值分析软件是提升我国快堆研发水平的基础。现阶段,我国仍沿用20世纪80、90年代以来通过消化、吸收形成的数值分析方法与计算软件,面临着计算模型近似大、适用范围窄等技术问题,亟待理论上的突破和新一代高性能数值分析软件的研发。为此,本文针对液态金属快堆研发的关键环节,提出了一套高精度数值模拟计算的方法模型,并研发了完全自主知识产权的计算软件系统。通过中国实验快堆测量数据以及设计参数对比分析,验证了模型的正确性和计算软件的先进性。Liquid-metal fast reactor is a key link between the preceding and the next in the “three steps”strategy of nuclear energy development in China.High-precision numerical analysis software of liquidmetal fast reactor is the basis for improving the research and development level of fast reactor in China.At present,the industry departments still use the numerical analysis methods and computing software formed through the digestion of imported software since the 1980s and 1990s,and face the technical problems such as large model approximation and narrow application range,and it is urgent for theoretical breakthrough and the research and development of a new generation of high-performance numerical analysis software.This paper focused on the physical characteristics and numerical analysis needs of liquid-metal fast reactor,focusing on six aspects:nuclear data processing,nuclear reactor physics,thermal hydraulics,system safety analysis,fuel performance analysis,and radiation shielding analysis.It proposed a set of numerical analysis methods for liquid-metal fast reactor with advanced theoretical models,high computational accuracy,and strong adaptability to reactor types.With the support of national projects,a fully independent code system,named LoongSystem,was developed.To validate the LoongSystem,the physical experiments and operational measurement data based on China Experimental Fast Reactor(CEFR) were utilized to verify the proposed theoretical model and the developed code system.The results indicate that the maximum error in critical calculations for the CEFR startup physical experiments is 321 pcm,and the maximum relative error in control rod value is 11.60%.The trends in the thermal hydraulics and system safety analysis calculations of the reactor core are consistent with the experimental measurement results,with relative deviations of key parameters such as outlet temperature being less than 2%.The aforementioned results indicate that the newly proposed model and the developed computational software exhibit e

关 键 词：液态金属快堆 软件开发 堆芯物理分析 热工水力 系统分析 

分 类 号：TL32[核科学技术—核技术及应用]