## 压水核反应堆反射层热传递的数值计算研究

Title   Numerical Simulation and Study on Heat Transfer of the
Fuel Rod reflector in Pressurized Water Reactor (PWR)
Abstract
The reactor core is the heart of equipment in nuclear power plant. Protecting the safety of the reactor core is the priority among priorities in the process of nuclear power plant operation. Guaranteeing the reactor core  in a suitable
cooling  condition,which is the premise of avoiding the leakage of radioactive substance.The numerical research on changing of source terms and temperature field changes has been done ,by using unstructured grid and FORTRAN program ,during  the process of the operation. 源`自*六)维[论*文'网www.lwfree.cn
Based on the one-group diffusion theory of uniform medium,singer cylinder fuel rod is taken into consideration. First of all, the fundamental equations are deduced and the fuel rod geometric model is established. By given two different boundary condition, the temperature distributions in normal condition are calculated and discussed. Next the temperature distributions of fuel rod with different reflector in normal operation condition are calculated and discussed. Finally, the comparisons of temperature distribution between fuel rod and fuel rod with reflector are made.
Keywords  Pressurized water reactor  Cylinder-shaped fuel rod  Reflector   Numerical calculation

1 引言 1
1.1研究背景及意义 1
1.2核反应堆研究现状  2
1.3本文主要研究工作  4
2 传热的基本概念与方程  5
2.1热传导微分方程  5
2.2圆柱坐标系  7
2.3球坐标系  8
3 数值模型的温度场分布  9
3.1传热控制方程  9
3.2 算例的数值计算与分析  11
3.3本章小结  16
4燃料棒反射层对温度分布的影响  17
4.1计算模型及网格  17
4.2计算结果及分析  18
4.3本章小结  21
结论  22

1 绪论
1.1 研究背景及意义

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