压水堆燃料销钉的中子学和热工水力学特性分析

M. Zakir, M. Sarkar, A. Hossain
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引用次数: 7

摘要

本文对压水堆燃料针电池级的焓、慢化剂温度、慢化剂密度、流速、压力和燃料温度分布等不同参数进行了比较分析。此外,在本文中,节距与燃料销的半径比在2.3到4之间变化。所述方法和实施策略使得以完全一维(1D)方式执行耦合的中子和热工水力学分析。热工水力学是基于慢化剂/冷却剂的质量和焓方程以及燃料棒的一组扩散方程。燃料针式电池和子通道的建模分两步进行。首先,假设方程中出现的所有参数都与温度无关,推导出控制方程。根据导热系数的傅立叶定律,导出了燃料销中心线温度和径向平均温度方程。最后,根据燃料棒温度对扩散系数、裂变截面和吸收截面进行了评估。这一结果将有助于PWR的中子学和热分析。热工水力学参数与最低值相差最大30%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Analysis of Neutronics and Thermal-Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PWR)
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.
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