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铅冷快堆多物理耦合分析方法及三维瞬态特性研究 被引量:1

Analysis of Transient Thermal-Hydraulic and Safety of Lead-Cooled Fast Reactor Based on Unified Coupling Framework
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摘要 为提高反应堆数值模拟的精度,基于通用程序耦合接口(ICOCO)规范与集成方法,构建了中子扩散程序(NDK)、子通道程序(KMC-SUB)以及计算流体力学(CFD)程序TrioCFD多尺度多物理耦合统一框架。通过对有源代码软件依照ICOCO规范进行封装并编写统一耦合调度程序,以中型模块化铅冷快堆(M2LFR-1000)为实例,研究了其在停堆工况和非对称无保护失流事故下的三维流动传热。研究结果表明,利用开发的多尺度多物理耦合分析工具能够更精确地捕捉铅冷快堆(LFR)的三维热工水力及整体现象。停堆工况下,上腔室出现明显的热分层现象;非对称无保护失流事故下,一回路热工参数发生明显震荡,且上腔室出现热分层、射流混合和再循环流动现象。 In order to improve the accuracy of the reactor numerical simulation,a unified framework of multi-scale and multi-physical coupling based on the ICOCO(Interface for Code Coupling)packaging and integration method is constructed by coupling the neutron diffusion code NDK,subchannel codes KMC-SUB and open-source CFD code TrioCFD.By encapsulating the source codes in accordance with the ICOCO specification and writing a unified coupling scheduling(SuperVisor)program,taking the medium-sized modular lead-cooled fast reactor M2LFR-1000 as an example,three-dimensional flow and heat transfer phenomenon under the shutdown condition and unprotected loss of flow accident are studied.The results show that the developed multi-scale and multi-physical coupling analysis tool can more accurately capture the three-dimensional T/H and overall phenomena of the lead-cooled fast reactor.Under the shutdown condition,obvious thermal stratification phenomenon occurs in the upper chamber.Under the asymmetric unprotected loss of flow accident,the thermal parameters of the primary circuit oscillate significantly,and the upper chamber exists thermal stratification,jet mixing,and recirculation flow phenomenon.
作者 罗晓 张喜林 陈红丽 王帅 郭超 王驰 Luo Xiao;Zhang Xilin;Chen Hongli;Wang Shuai;Guo Chao;Wang Chi(University of Science and Technology of China,Hefei,230026,China;Nuclear Power Institute of China,Chengdu,610213,China;China Academic of Engineering Physics,Mianyang,Sichuan,621900,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2021年第S01期11-16,共6页 Nuclear Power Engineering
基金 “核反应堆系统设计技术国家重点实验室”资助
关键词 耦合框架 铅冷快堆(LFR) 多尺度多物理 热工水力 Coupling framework Lead cooled fast reactor(LFR) Multi-scale and multi-physical Thermal-hydraulic
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