钠冷快堆中间热交换器模型的不确定度研究  

Study on Uncertainty of Middle Heat Exchanger Model for Sodium Cooled Fast Reactor

作　　者：李健捷 张东辉[1] 王利霞[1] 叶尚尚[1] 王晋[1] 杨军[1] 刘一哲[1] LI Jianjie;ZHANG Donghui;WANG Lixia;YE Shangshang;WANG Jin;YANG Jun;LIU Yizhe(China Institute of Atomic Energy,Beijing,102413 China)

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《科技创新导报》2020年第23期111-113,共3页Science and Technology Innovation Herald

摘　　要：核安全已成为人们日益关注的重大问题,不确定度评估是核反应堆最佳估算安全分析中的重要一环。本文概述了池式钠冷快堆CFR600中间热交换器的一维单管模型,并针对该模型,考虑了几何、物性、边界条件等输入参数不确定度的影响,分别利用基于改进的拉丁超立方抽样方法的统计类与基于正态误差传播公式的确定类分析方法,计算并对比分析了输出结果的不确定度。分析表明,两种方法适用性强、计算代价不高,二者不确定度评估结果非常吻合,在选定的输入参数分布下,给出了输出的标准不确定度和扩展不确定度。在95%的置信水平下,壳侧出口温度Tp,out的扩展不确定度不超过6.0℃,管侧出口温度Ts,out的扩展不确定度不超过4.5℃。Nuclear safety has become an important issue that people pay more and more attention to.Uncertainty evaluation is an important part in the safety analysis of the best estimate of nuclear reactor.In this paper,a onedimensional single tube model of the intermediate heat exchanger of pool type sodium cooled fast reactor(cfr600)is summarized.Considering the uncertainty of input parameters such as geometry,physical properties and boundary conditions,the statistical class based on the improved Latin hypercube sampling method and the deterministic class analysis method based on the normal error propagation formula are used to calculate and compare the uncertainty of the output.The analysis shows that the two methods have strong applicability and low calculation cost,and the evaluation results of the two methods are very consistent.Under the selected input parameter distribution,the standard uncertainty and expanded uncertainty of the output are given.At the 95%conf idence level,the expanded uncertainty of shell side outlet temperature TP,out is not more than 6.0℃,and that of tube side outlet temperature Ts,out is not more than 4.5℃.

关 键 词：钠冷快堆 不确定度 中间热交换器 拉丁超立方抽样 误差传播公式 

分 类 号：TL35[核科学技术—核技术及应用]