文档介绍：本科生毕业论文(设计)
题目核电常规岛高压加热器设计与研究
学院化学工程学院
专业过程装备与控制工程
学生姓名李朝
学号 0843082075 年级 2008 级
指导教师黄卫星教授
教务处制表
二○一二年五月二十四日
四川大学本科毕业设计——核电常规岛高压加热器设计与研究
核电常规岛高压加热器设计与研究
专业过程装备与控制工程
学生李朝指导教师黄卫星教授
摘要:核电常规岛高压加热器是利用汽轮机抽汽加热进入核岛蒸汽发生器高压给水,
提高核电厂热力循环效率,降低蒸汽发生器传热温差,保证机组安全运行的一种管壳
式换热器。目前,国内企业基于火电高压加热器的设计经验并借鉴国外设计图纸对核
电高压加热器做了一定自主研制,但存在结构不够紧凑,换热不够高效的问题。本文
按照 GB150-1998 和 GB151-1999 对高压加热器各个结构部件进行设计与强度校核,绘
制了高压加热器设备总图和管系等图;在此基础上,将高压加热器分为三个串联换热
器,建立联立方程组,探究气相、汽液两相、液相三种流体介质在换热管外传热系数,
建立了传热设计计算的迭代法与过程;基于管束冷凝传热分析结果,提出了在管板布
管区减少换热管数留出蒸汽通道、部分换热管设置引流翅片、MSR 进口设置独立扩容
室等结构优化方案,以提高加热器传热效率。
关键词:核电站; 高压加热器;强度校核;热力计算;结构优化
四川大学本科毕业设计——核电常规岛高压加热器设计与研究
Design and Research of High-Pressure Heater of the
Conventional Island of Nuclear Power Station
Major:Process Equipment and Control Engineering
Student: Li Zhao Supervisor: Prof. Huang Weixing
Abstract:High-pressure heater of the conventional island of nuclear power is a shell-tube
heat exchanger,whose role is to heat the high-pressure water from turbine extraction steam,
it could ensure the temperature of feed water which will rise the thermodynamic cycle
efficient of nuclear power plant and reduce temperature difference of the steam generator to
ensure the safe of operation unit. At present, domestic enterprises did some independent
research based on the thermal power design experience and learn from the foreign design
drawings, but the structure is pact enough. Designed and checked the strength of the
various ponents of the high pressure heater in accordance with GB150-1998
and GB151-1999; divided high pressure heater into three series heat exchangers,
simultaneous equations, explore the heat transfer coefficient of gas, vapor-liquid two-phase
liquid these three fluid medium in the heat exchange tubes rumor, use iterative method to
find a set of heat transfer formula. Based on these results, reducing some heat transfer tubes
to stay out of the steam channel, set the drainage fin on part of the heat exchange t