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首页> 外文期刊>World Journal of Nuclear Science and Technology >Analysis of Neutronics and Thermal-Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PWR)
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Analysis of Neutronics and Thermal-Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PWR)

机译：压水堆（PWR）燃料销中的中子学和热工液压行为分析

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摘要

This paper presents a comparative analysis of different parameters such as enthalpy, moderator temperature, moderator density, flow velocity, pressure, and fuel temperature profile at the fuel pin cell level of PWR. Moreover, in this paper pitches to fuel pin radius ratio are varied from 2.3 to 4. The methods and implementation strategy are such that the coupled neutronic and thermal-hydraulic analysis is executed in a fully one dimensional (1D) manner. The thermal hydraulic is based on moderator/coolant mass and enthalpy equation together with one group diffusion equation for fuel pin. Modelling of fuel pin cell and subchannel is executed in two steps. First, the governing equations are derived assuming that all the parameters appearing in the equations are temperature independent. Fuel pin centerline temperature and radially averaged temperature equations are derived from Fourier laws of thermal conductivity. Finally, diffusion coefficient, fission cross-section and absorbing cross-section are evaluated with respect to the fuel pin temperature. The outcome will be helpful for further neutronics and thermal analysis of PWR. Thermal hydraulics parameter varies the maximum 30 percentage from the lowermost value.
机译：本文介绍了在PWR燃料销电池水平上不同参数的比较分析，例如焓，调节剂温度，调节剂密度，流速，压力和燃料温度曲线。此外，在本文中，节距与燃料销的半径比从2.3变为4。方法和实施策略应以完全一维（1D）的方式执行中子和热工液压耦合分析。热液压基于减速器/冷却剂质量和焓方程以及燃料销的一组扩散方程。燃料pin电池和子通道的建模分两个步骤执行。首先，假设方程中出现的所有参数与温度无关，则推导控制方程。燃料销中心线温度和径向平均温度方程式是根据傅里叶热导率定律得出的。最后，针对燃料销温度评估扩散系数，裂变截面和吸收截面。该结果将有助于进一步对压水堆进行中子学和热分析。热力液压参数从最低值起最大改变30％。

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