摘要保证核电站安全的重要部位就是核反应堆堆芯，能将核反应堆堆芯在反应过程中产生的热量及时散出就能很大程度的确保核电站的安全问题。热源分布取决于堆的具体设计，即堆型种类﹑堆芯的形状以及反应堆燃料棒﹑调节棒﹑慢化剂制冷剂和反射层的安置。在此采用非结构化网格中有限体积方法，运用可视Fortran90/95高级软件开发工具, 数值计算分析先进PWR堆堆芯燃料棒的内热源和温度场分布。对于燃料棒模型本文建立了圆柱体和六棱柱两类，在第三章对该两类模型两端给定定温或者绝热两类边界条件然后进行温度数值分析，对比两模型的温度分布图可知，二者温度分布走势大致一样，只是圆柱体燃料棒模型温度最高值大于六棱柱燃料棒。83247
在第四章分析了影响堆芯内热源的三种因素变化对燃料棒各位置温度值的影响。未插入控制棒时，运行稳定温度略高于正常运行时燃料棒温，需对其最高温度格外注意，不能超出安全值；之后还比较了在引入正反应或者负反应后燃料棒同一位置处温度随时间的改变情况。
毕业论文关键词：圆柱体，六棱柱，PWR堆，数值计算
毕业设计说明书外文摘要
Title PWR reactor fuel rods thermal reavtion calculation and analysis
Abstract The heat released from nuclear reaction being transferred promptly from the reactor core, can in a great extent to ensure the nuclear power plants safety。
Its distribution depends on the reactor types , core shape and placement of the reactor fuel rods。 Unstructured grid finite volume method is taken to do research on the advanced PWR reactor core fuel 。 With advanced visualization development tools , Fortran90 / 95 software, this study focuses on the analysis the of internal heat source and the temperature field distribution through numerical
computation。Two fuel rod models are established:the cylinder and the hexagonal prism。In the third chapter this two models are given the constant temperature or adiabatic boundary conditions at both ends to conduct the temperature numerical analysis。With comparison of the two models temperature distribution,apart from that their temperature distribution trend roughly the same。
The influence of the three factors on the location of the fuel rods is analyzed In the fourth chapter。It indicates that with the control rod not inserted
temperature of the fuel rod is slightly higher than that of the normal operation。Attention is bound to be paid to keep the maximum temperature from exceeding the safety value 。 Comparison have also been made about the fuel rod temperature variation with time,at the same position,of the positive and negative reaction introduction 。
Key: Pressurized Water Reactor Cylindrical fuel rods Hexagonal prism fuel rods Numerical Heat Transfer
目 次
1 绪论 1
1。1 研究背景与意义 1
1。3 本文主要研究工作 2
2 堆芯传热的基本概念 4
2。1 热传导微分方程 4
2。2 圆柱坐标系 6
3 计算模型对温度分布的作用 8
3。1 传热控制方程的解析解 8
3。2数值计算与分析 10
3。3 本章小结 Fortran的PWR堆燃料棒热反应性计算与分析:http://www.youerw.com/wuli/lunwen_98015.html