本科生毕业论文(设计)题 目核 电 常 规 岛 高 压 加 热器 设 计 与 讨 论学 院化 学 工 程 学 院专 业过程装备与控制工程学生学 号年 级指 导 老 师核 电 常 规 岛 高 压 加 热 器 设 计 与 讨 论专 业 过程装备与控制工程摘 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。本文根据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Design and Research of High-Pressure Heater of theConventional Island of Nuclear Power StationMajor：Process Equipment and Control EngineeringAbstract ： 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 not compact enough. Designed and checked the strength of the various structural components of the high pressure heater in accordance with GB150-1998 ...
