【作者】 李媛媛； 张敏； 任瑞琪；

【Author】 LI Yuan-yuan,ZHANG Min,REN Rui-qi (School of Energy & Power,Nanjing University of Science & Technology,Nanjing of Jiangsu Prov.210094,China)

【机构】 南京理工大学能源与动力学院；

【摘要】 基于压水核反应堆燃料棒稳态导热偏微分方程的一般形式,通过积分推导求得其近似解。该核燃料棒具有不均匀的内热源分布,即径向为贝塞尔函数分布,轴向为余弦函数分布。同时,以先进型压水堆AC-600为原型,在非结构化网格中采用有限容积方法,对非正交控制元进行基本扩散项和二次扩散项的交替迭代,数值计算燃料棒的传热状况。将数值计算所得结果与热传导方程的积分近似解进行比较验证和误差分析,在此基础上分析了燃料棒的温度场分布情况和变化规律,得到燃料棒最高温度的大小及出现的位置。本研究可以为核反应堆热工设计和热防护提供有益参考。更多还原

【Abstract】 Based on the differential form of the general heat conduction equation,the approximating expression for a nuclear fuel rod was derived through integral.The fuel rod has asymmetrical heat resource distribution.Bessel function distribution is in radial direction and Cosine function distribution is in axis direction.Also,using the model of the advanced pressure water reactor 600,and taking an iterative calculation between tangential and normal diffusion terms in every control cell,temperature distribution of the fuel rod was computed by the finite volume method(FVM) in the unstructured grids.Comparing the approximate solutions with the numerical results,there was a good agreement between them.On this condition,we derived the location and size of maximum temperature by analysis the temperature distribution and variation.All of these can provide a useful reference for the pressure water reactor thermal design and thermal protection of nuclear engineering.更多还原