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核电站堆芯温度场软测量方法研究
引用本文:陆彬,姜懿纯,朱小良. 核电站堆芯温度场软测量方法研究[J]. 传感技术学报, 2016, 29(2): 226-231. DOI: 10.3969/j.issn.1004-1699.2016.02.013
作者姓名:陆彬  姜懿纯  朱小良
作者单位:东南大学能源与环境学院,南京,210096;东南大学能源与环境学院,南京,210096;东南大学能源与环境学院,南京,210096
摘    要:核电站堆芯内部温度是反应堆安全运行的重要参数,由于受到测点安装条件的限制,无法直接测量。为解决该问题,在现有压水堆堆芯功率模型的基础上,结合稳态传热热量守恒方程,构建堆芯温度场的计算模型,推算出堆芯内部温度。并通过数值模拟计算结果与堆芯出口实测值的比较,运用数据不确定度作为判断依据,验证了方法的可行性,得到了堆芯内部不同截面的二维温度分布图,为堆芯内部温度的实时监测提供了理论依据。

关 键 词:压水堆堆芯  堆芯温度  数值模拟  稳态传热  温度测点

Study of Temperature Field Reconstruction in Reactor Core of Nuclear Power Plant
LU Bin,JIANG Yichun,ZHU Xiaoliang. Study of Temperature Field Reconstruction in Reactor Core of Nuclear Power Plant[J]. Journal of Transduction Technology, 2016, 29(2): 226-231. DOI: 10.3969/j.issn.1004-1699.2016.02.013
Authors:LU Bin  JIANG Yichun  ZHU Xiaoliang
Abstract:The temperature in reactor core of nuclear power plant is an important parameter for reactor safety opera?tion,which cannot be directly measured because of the restriction on installation conditions of measuring points. To solve the problem,On the basis of the existing model of the core power of the pressurized water reactor,the calcula?tion model of the core temperature field is constructed with the steady state heat transfer heat conservation equation , and core internal temperature can be calculated. And by comparing the results of numerical simulation with the measured value of core outlet,using data uncertainty as the basis for judgment,the feasibility of the method is veri?fied,and the two dimensional temperature distribution of different section of the core is obtained. It provides theoret?ical basis for the real-time monitoring of the internal temperature of the core.
Keywords:pressurized water reactor core  core temperature  numerical simulation  steady state heat transfer  tem-perature measuring point
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