《断电事故下核主泵流动及振动特性研究》由会员分享，可在线阅读，更多相关《断电事故下核主泵流动及振动特性研究（104页珍藏版）》请在金锄头文库上搜索。
1、上海交通大学 硕士学位论文 断电事故下核主泵流动及振动特性研究 姓名：刘夏杰 申请学位级别：硕士 专业：核能科学与工程 指导教师：王德忠;张继革 20080201 上海交通大学硕士学位论文 1 断电事故下核主泵流动及振动特性研究 摘 要 目前，国内在建和运行的反应堆核主泵均依赖进口，核主泵是我国 核电技术自主化和设备国产化的瓶颈。核主泵作为反应堆一回路压力边 界的组成部分，又是核岛内唯一的关键旋转设备，要求在高温、高压、 放射性环境下长期、安全、可靠地运行，技术难度极高。本文针对核主 泵在断电情况下的流动及振动特性开展了研究。 本文围绕核主泵设计、制造等相关问题进行深入的调研，重点比较 了美国
2、 ASME- III和法国 RCC- M 标准之间的区别，对国内外核电标准、 安全评价、关键技术等的发展情况进行了综述，对国内核主泵设计、制 造及标准建立具有一定的参考价值。 采用 Pro/E 软件边界混合功能对核主泵叶轮叶片进行三维建模，用 Ansys 软件对叶轮、转子进行了模态分析，获得它们的固有频率及振动 型式，并进一步计算了转子的临界转速、转动惯量等重要安全评价参数， 为今后对转子系统的动力响应分析及地震响应分析奠定基础。 通过核主泵的断电试验测得了瞬态振动、惰转流量、惰转转速等数 据，得出了断电事故情况下核主泵流量、转速的惰转规律曲线以及轴承 座、转轴的振动特性曲线，试验表明，断电事
3、故对核主泵流动及振动都 造成一定的影响，并对今后核主泵安全稳定运行存在潜在危害，试验结 果有助于认识核主泵在发生断电事故时的运行特性；进一步对惰转流量 上海交通大学硕士学位论文 2 曲线、惰转转速曲线进行了四次多项式拟合，拟合结果作为接下来流场 模拟的初始条件输入。 对核主泵全三维流场进行了模拟，得到了正常运行、偏离运行工况 及断电事故工况下的泵内流动特性，获得了包括叶轮、导叶、泵壳、泵 轴向切面、径向切面等的压力、速度矢量、粒子迹线等直观图形，研究 表明，在叶片背面中下部靠近轮毂处存在低压区，此部位存在明显的回 流及较大的流动损失，此正是泵内最容易发生汽蚀的部位，因此在设计 时应引起足够重视
4、；通过研究进一步获得了核主泵流量 Q压头 H、流 量 Q效率等特性曲线，与试验特性曲线比较发现，在偏离运行工况 时误差较大，这可能是在由于泵壳轴向进、径向出的特殊形状导致了在 偏离运行工况时产生更多流动损失所致；再通过表面积分功能获得了叶 轮轴向受力的变化情况，为核主泵的优化设计、安全评价及推力轴承的 设计提供有价值的参考。 关键词：核主泵，核安全，断电事故，安全评价，模态分析 上海交通大学硕士学位论文 3 Flow and Vibration Characteristic Research of Nuclear Main Pump under Station Blackout Acciden
5、t Abstract At present, in China, the nuclear main pumps in all the nuclear reactors in operation and construction rely on imports. The nuclear main pump has been the bottleneck to independent nuclear power technology and domestic manufacture. The nuclear main pump is a component of the primary loop
6、pressure boundary and the only critical rotating equipment in nuclear island, its security, stability, and long- term reliable operation requirements in high- temperature, high- pressure and radiation conditions. It s a high technology system. Studies mainly on nuclear main pump are conducted in thi
7、s paper from the flow and vibration point of view under station blackout accident. In this paper, in- depth researches are conducted on the design, manufacturing, and other relative issues of nuclear main pump. The differences between ASME- III of United States and RCC- M of France are compared spec
8、ifically. The development of nuclear standards, safety evaluation, and key technologies etc. in and out of country are summary described. This work has a certain reference value to the design, manufacturing of nuclear main pump and the standard construction. 3D models of nuclear main pump impeller a
9、nd blade are constructed by surface blending function of Pro / E software, Use Ansys software for the modal analysis of the impeller and rotor, obtaining their natural frequencies and mode shapes, further calculated the important safety evaluation 上海交通大学硕士学位论文 4 parameters such as rotor critical spe
10、eds and moment of inertia, which lay the foundation for the future analysis on dynamic response and earthquake response of the rotor system. Through station blackout test of nuclear main pump, the transient vibration, idle flow, idle rotate- speed and other data is measured; the idle rule- curves of
11、 flow, rotate- speed and vibration characteristics on housings and shaft are obtained. The test shows that the station blackout accident has certain affection to flow and vibration in nuclear main pump, and has potential hazards to the future security and stability operation in pump. The test result
12、s help to understand the operational characteristics of nuclear main pump under station blackout accident. Further works are done on the fourth polynomial curve fitting to idle flow and idle rotate- speed, fitting result as an initial importation conditions in following flow simulation. Nuclear main
13、 pump s full 3D simulation of the flow field is conducted; flow characteristics in pump are obtained in the normal operating, deviate from normal operating and station blackout accident conditions; the intuitive graphics of pressure, velocity vector, and particle trace lines in pump including impell
14、er, guide vanes, pump shell, pump axial section and radial section. Research shows that in the blade around the bottom of the back wheel exists a low pressure area, on which has an obvious flow return and large hydraulic loss, and it is the easiest location to produce cavitations, thus, the design s
15、hould pay sufficient attention. Through further research, flow Q- pressure head H, flow Q- efficiency curves of nuclear main pump characteristic are obtained, compared with the experimental curves, discovered that there is much more relative error while deviate from the operation conditions, this is
16、 probably due to the axial entrance and radial 上海交通大学硕士学位论文 5 export of pump, and this special shape produces more hydraulic loss while operating in deviate from normal conditions. Through the surface integral function, the axial force changes on impeller is obtained, which can provide valuable reference to optimized design, safety assessment and the design of thrust bearing of nuclear main pump. KEY WORDS: nuclear main pump, nuclear safety, station blackout, safety assessment, modal anal
