新型兆瓦级热管堆热管失效事故分析  

Heat pipe failure accident analysis of a new type of megawatt heat pipe reactor

作　　者：汪镇澜 苟军利[1] 徐世浩 王政 单建强[1] 郭斯茂 唐彬[2] WANG Zhenlan;GOU Junli;XU Shihao;WANG Zheng;SHAN Jianqiang;GUO Simao;TANG Bin(School of Nuclear Science and Technology,Xi'an Jiaotong University,Xi'an 710049,China;Institute of Nuclear Physics and Chemistry,China Academy of Engineering Physics,Mianyang 621000,China)

机构地区：[1]西安交通大学核科学与技术学院,西安710049 [2]中国工程物理研究院核物理与化学研究所,绵阳621000

出　　处：《核技术》2022年第11期110-120,共11页Nuclear Techniques

基　　金：国家重点研发计划课题(No.2019YFB1901204)资助。

摘　　要：热管堆具有良好的固有安全性,在堆芯概念设计初期,热管失效事故通常是需要被考虑的设计基准事故之一。本文基于FLUENT软件研究了一种新型兆瓦级热管堆堆芯的核热性能,建立了点堆中子动力学模型、堆芯及热管传热模型和堆芯内腔辐射换热模型,完成了三维堆芯额定工况和热管失效事故工况下的核热计算。通过将堆芯各组件的峰值温度与对应的材料熔点进行比较,对堆芯安全性能进行评估。结果表明:额定工况和单根热管失效事故下该堆具有良好的安全性;较严重的高功率区三根热管串级失效事故下内腔辐射换热不可忽略;同时,该堆不能承受高功率区的四根热管串级失效;通过将多根热管失效后的峰值温度与单根热管失效后的峰值温度比较,反映了该堆的良好固有安全性。[Background]Heat pipe cooled reactors(HPR)have good inherent safety.In the early stage of core design,heat pipe failure accident is usually one of the design basis accidents that need to be considered.[Purpose]This study aims to analyze the neutronic-thermalhydraulic coupling performance of a new type of megawatt heat pipe reactor.[Methods]Firstly the heat pipe cooled reactor system physical models,including the point kinetics model,the core and heat pipe model and radiation heat transfer model for the inner core cavity,were established according to the designed HPR prototype composed of heat pipe stack and supercritical CO_(2)Brayton cycle system with thermal power of 3.5 MW.Then,the finite element software FLUENT was employed to conduct neutronic-thermalhydraulic coupling calculation for the three-dimensional reactor core under the steady-state and heat pipe failure accidents.Finally,the core safety performance was evaluated by comparing the peak temperature of each component with the melting point of material.[Results&Conclusions]The results show the designed HPR has good safety performance under the steady state and single heat pipe failure.Radiation heat transfer in the core cavity cannot be ignored in the serious cascade three heat pipe failure accident in high power region.Meanwhile,the design cannot withstand cascading four heat pipe failure.By comparing the peak temperature of the multiple heat pipe failure with the peak temperature of the single heat pipe failure,it shows that the design has good inherent safety.

关 键 词：热管堆 热管失效事故 核热计算 串级失效 固有安全性 

分 类 号：TL33[核科学技术—核技术及应用]