摘要核能作为当今世界的一种清洁能源，对满足能源的需求、能源结构的调整、减少环境污染和经济的发展有重要的作用。然而核电就像带刺的玫瑰，既可以带来爱情，也能让人遍体鳞伤。所以核电的发展需要对其进行核安全分析。核反应堆有核电站的心脏之称，本文将以 AC-600 先进压水堆为例，对反应堆燃料棒的传热进行数值计算。
运用可视Fortran90/95 高级软件开发工具,进行先进压水堆燃料棒传热的数值分析计算。棒体内部生成非结构化网格，对反应堆堆芯的热环境和温度场分布进行数值模拟。燃料棒外流场采用工程方法，计算层流与紊流的热通量分布。 依据能量守恒方程和傅里叶定律求得热传导在三类坐标系下的偏微分方程。以堆芯内的一根燃料棒为例，分别通过751棱柱体与圆柱体两种模型进行分析。求出稳态热传导时圆柱体燃料棒偏微分方程的解析解。通过有限容积法在非结构化网格里数值计算燃料棒内温度场。
随着控制棒插入深度的变化，反应堆处于不同的运行状态，内热源也随之变化。 可发现，燃料棒温度在控制棒未插入情况下明显较高。然后研究反应堆运行时，堆芯温度变化而导致的温度场变化。最后对燃料棒外流场进行工程计算，对层流、紊流和过渡区三种流动状态进行数值计算，以更贴近工程实际。19285
关键词: 先进压水堆 燃料棒 数值模拟
Title Numerical Simulation and Study on Heat Transfer of
Fuel Rods in Pressurized Water Reactor (APWR)
Abstract
As a clean energy source, nuclear energy plays an important role in the
world today in meeting the demand for energy, the structure adjustment,
reducing environmental pollution and economic development. However,
nuclear power is like a rose with thorns which can not only bring love but
also make people seriously wounded. So nuclear safety analysis is the
primary condition for development of nuclear power. A nuclear reactor is
the heart of a nuclear power plant. Taking advanced pressurized water
reactor AC-600 for example, numerical calculations on heat transfer of the
reactor fuel rods have been done.
Numerical analysis on heat transfer of the reactor fuel rods have been done
using visual Fortran 90/95 Senior Software Developer tools. Rod internal
use unstructured grid numerical method to simulate thermal environment and
temperature distribution of the reactor core numerically. Analyze heat
flux distribution of the laminar, transition, turbulent regions in the
external flow field by engineering method.
Based on Fourier law and energy conservation equations, partial
differential equation of heat conduction in three types of coordinate
systems are derived. Conducting research on a single fuel rods, the
different boundary conditions and the geometry size (cylinder and
six-rowed column) are taken to consider. Obtain analytical solution of
steady-state partial differential equation of heat conduction of cylinder.
In unstructured grid, simulate the temperature distribution within the
fuel rods by finite volume method.
As the depth of insertion change in control rod, the reactor is at different
operating states. So does the heat. We could found when the control rod
is not inserted, the fuel rod temperature is significantly higher. When
the reactor is operating, changes in temperature field vary with core
temperature. Last, the regions of flows were researched considering the
facts. Analyze the laminar, transition and turbulent regions by
engineering method respectively.
Key word: APWR, fuel rod, numerical simulation.
目 次
1 绪论 1 APWR堆燃料棒热传递的数值计算与研究:http://www.751com.cn/wuli/lunwen_10583.html