静默式热管反应堆热工水力特性不确定性分析  

Uncertainty Analysis of Thermal-hydraulic Characteristics of Silent Heat Pipe Cooled Reactor

作　　者：韩睿钰 王成龙[1] 郭凯伦 苏光辉[1] 秋穗正[1] 田文喜[1] HAN Ruiyu;WANG Chenglong;GUO Kailun;SU Guanghui;QIU Suizheng;TIAN Wenxi(Department of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,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

出　　处：《原子能科学技术》2023年第5期998-1006,共9页Atomic Energy Science and Technology

基　　金：国家自然科学基金(U20B2012)。

摘　　要：基于不确定性分析软件DAKOTA和自编程热管反应堆单通道热工分析程序HEART,对静默式热管反应堆(NUSTER)稳态热工水力特性进行了不确定性分析。根据热管反应堆相关实验数据,选取运行功率、燃料热导率、气隙宽度、包壳厚度、热管蒸发段长度和基体厚度6个关键热工参数并确定其基准值与概率密度分布,通过大量重复性计算,获得了95%置信水平下热管蒸发段温度、热管冷凝段温度、燃料峰值温度、包壳峰值温度及基体温度的统计分布,并对各参数的不确定性对热管反应堆安全性的影响进行了分析。分析结果表明:热管蒸发段及冷凝段温度有0.67%的概率超过热管温度限值;由于热管反应堆堆芯为固态堆芯,传热以纯导热为主,输入变量的不确定性对不同目标参数的影响相同,燃料热导率的不确定性对5个目标参数的影响最为显著,且为负相关。本研究获得的结果可为热管反应堆的优化及其后续发展提供方向指引。Uncertainty analysis has a significant meaning in reactor design,analysis and safety assessment.Based on the uncertainty analysis program DAKOTA and the self-programmed heat pipe cooled reactor single channel thermal analysis program HEART,the steady-state thermal-hydraulic characteristics of silent heat pipe cooled reactor(NUSTER)were analyzed.In order to ensure that the calculation results have reference value,the validity of DAKOTA and HEART was verified.Heat pipe cooled reactor is a new hot type of nuclear reactor rising in recent ten years.Compared to many other reactor concepts,heat pipe cooled reactor has many unique characteristics,such as solid core,passive heat transfer,high power density,low operating noise.Based on the phenomena identification and ranking table(PIRT),design parameters and relevant experimental data of heat pipe cooled reactor,six thermal parameters,including operating power,fuel thermal conductivity,air gap width,cladding thickness,heat pipe evaporator length and matrix thickness were selected,and their reference values and probability density distributions were determined.The statistical distributions of heat pipe evaporator temperature,heat pipe condenser temperature,fuel peak temperature,cladding peak temperature and matrix temperature at 95%confidence level were obtained through a lot of repeated calculations,and the influence of the uncertainty of each parameter on the safety of heat pipe cooled reactor was analyzed.The result shows that fuel peak temperature,cladding peak temperature and matrix temperature are far below their temperature limits,while the temperature of both evaporator and condenser of heat pipe has a probability of about 0.67%exceeding the temperature limit of heat pipe.These indicate that the current heat pipe cooled reactor design may have the potential risk of the heat pipe failure,even though the probability is fairly low for steady-state.Further design optimizations thus become necessary for lowering the heat pipe failure probability.What’s more,according

关 键 词：热管反应堆 不确定性分析 DAKOTA 

分 类 号：TL333[核科学技术—核技术及应用]