蒸汽发生器的建模及仿真刘奕知
第35卷第11期（2016.11）：
技术纵横
摘要：蒸汽发生器能否正常运行直接关系到整个核电站的安全运行。根据蒸汽发生器的结构原理，将蒸汽发生器划分为16个控制体，把蒸汽发生器的上升通道划分为过冷区和沸腾区。为了更好地反映蒸汽发生器的动态过程，在过冷区和沸腾区之间引入了可移动边界。在Matlab软件中用编制好的算法和图元搭建蒸汽发生器仿真模型。给出初始状态下的给水流量进行仿真实验，利用阶跃上升的给水流量做动态扰动实验，得出一次侧冷却剂出口水室温度变化的响应曲线和二次侧蒸汽压力的响应曲线，仿真实验的响应曲线与实际蒸汽发生器工作时的物理状态一致。该数学模型和仿真程序可以反映出蒸汽发生器运行阶段一次侧、二次侧动态响应过程，对蒸汽发生器设计以及装置事故分析有一定的参考价值。
关键词：蒸汽发生器；工作原理；数学模型；仿真实验 Doi : 10.3969/j.issn.10066896.2016.11.024
The Modeling and Simulation of Steam Generator Liu Yjia
Abstract: The safety of the nuclear power plant operation directly depends on the working status of Steam Generator (SG). The steam generator is divided into 16 control volumes ac cording to its structure and principles, and divided the rise of the steam generator for cold ar ed and boiling ared. The risen channel of the steam generator is divided into subcooling sec tion and superheat section.
ln order to get better reflection of SG's dynamic process, a
movable boundary has been set between them.
Programmed algorithm and drawing units
were used in matlab to build simulation model of the steam generator.
Doing step up feed
water flow dynamic disturbance test under the given initial state of feed water flow simula tion, the primdry side coolant outlet water chamber temperature response curves and the sec ondary side of steam pressure decreased response curve can be obtained.Response curves of the simulation results and the actual physical working state of SG are the same. This mathe-matical model and simuleation program can reflect the primary side and secondary side dynamic response process of SG in operation stage,
which could have certein reference value in SG
design and equipment accident analysis.
Key words: steam generator; mathematical model; simulation test; working principle
在压水堆核电站中一回路和二回路的换热是通过蒸汽发生器进行的。作为一回路和二回路之间的枢纽，蒸汽发生器的作用不仅仅是将一回路冷却剂从堆芯带出的热量传给二回路，它还是分隔一次制和二次侧工质的屏障，蒸汽发生器能否正常运行直接关系到整个核电站的安全运行。
蒸汽发生器在给水流量尤其是蒸汽流量大范围变化时，会出现“虚假液位”现象，绝大部分紧急"上海交通大学自动化系
油气田地面工程https/wwwayqtdmgc.com 万方数据
停堆事件都是因“虚假液位”造成的。美国在役压水堆电站调查表明，核电站停堆事故有30%以上是由于蒸汽发生器主给水系统发生故障，即液位控制不良引起的。非预期的紧急停堆会降低核电站可用性，造成巨大的经济损失，因而蒸汽发生器在核动力装置事故中居重要地位，严重影响着核动力装置运行的安全可靠性"。
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