## 压水核反应堆燃料棒热传递的数值计算研究

针对燃料棒传热研究，运用两种不同的方法进行分析计算，从而绘制出数值解和精确解的温度场分布情况。最后的误差分析说明了本近似解有较高的准确性，可以应用在工程估算中，也对核燃料棒的固有安全性设计提供了依据和有益的参考。

Abstract
After the accidents of Nuclear Power Plant, the nation thought that the development of nuclear power must put safety the first. This study which gave an analysis on the numerical heat transfer of fuel rod. It analyses and draws the conclusion that what can strengthen the safety of the use of nuclear.
This study was in the unstructured grids, and the unsteady heat conduction equation was discretized from the fully implicit finite volume method. The programs that were created by FORTRAN completed the temperature computation and heat transfer disciplinarian of different situations. All the conclusions provided useful references for the thermal design and passed judgment on reactor inherent safety.
Two different methods were used in this study to analyze the numerical heat transfer of fuel rods .in this way, curve plotting of the numerical solutions and the exact solutions.

Last, error analysis declared that the approximate solution were highly accurate for the use of engineering cost estimate. what’s more , it can provided useful references for the thermal design and passed judgment on reactor inherent safety .
Keywords  pressurized water reactor ,numerical heat transfer,approximate  solution

1  绪论 1
2  数值计算的基本概念 3
2.1  网格的生成  3
2.2  控制方程的离散  4
2.3  热源项的处理   7
2.4  边界条件的处理  8
2.5  本章小结  11
3  均匀反应堆的临界理论  12
3.1  均匀反应堆的单群扩散方程 12
3.2  热中子反应堆的临界条件  14
3.3  燃料棒的几何曲率和中子通量密度  15
3.4  圆柱形反应堆的释热率分布    19
3.5  本章小结    20
4  三种工况下堆芯传热的数值计算  21
4.1 堆内释热率的分布方程  21  4.2 堆内温度场的数值求解  22
4.2.1 几何模型及网格 22
4.2.2 恒壁温条件下的温度求解  23
4.2.3 绝热边界条件下的温度求解   24
4.2.4 对流边界条件下的温度求解   26
4.3 本章小结    28
5  燃料棒传热的数值研究分析   29
5.1  几何模型与计算条件 29
5.2  核燃料棒传热偏微分方程的近似求解  31
5.3  算例的数值计算与分析 31
5.4 本章小结 35
6   结论  36

图2.2.2控制体单元矢量示意图 6

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