Research on the Control Technology of Automatic Start-up for PWR Nuclear Power Plant
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摘要: 为提高压水堆核电厂机组在启动过程中的自动化水平,减轻反应堆运行人员的工作强度,缩短启动时间,提高机组启动的正确性和规范性,本研究提出了一种适用于核电厂自动启动的控制技术,该技术方案基于典型压水堆核电厂机组系统自身特性,以及运行管理流程和自动启动的控制需求,通过对压水堆自动启动控制系统适用的控制范围、运行断点、顺序控制和模拟量控制等的分析研究,建立了用于压水堆核电厂自动启动的控制系统架构,具体包括架构结构设计、每个层级的功能和设计内容以及层级间的交互接口设计等。同时建立了典型压水堆核电厂自动启动仿真验证平台,以核电厂运行模式Ⅲ启动流程为例设计了自动启动控制系统,并对所提出的技术方案进行了仿真验证。仿真结果表明该自动启动控制系统能够实现核电厂运行模式Ⅲ自动启动,减少了运行人员的操作步骤和工作负担;设计搭建的核电厂自动启动控制系统架构可为核电厂自动启动控制系统应用提供参考,对提升核电厂机组的启动过程自动化水平具有重要意义。Abstract: To improve the automation level of PWR nuclear power plant units during startup, reduce the work intensity of reactor operators, shorten the start-up time, and improve the correctness and standardization of the unit start-up, this study puts forward a control technology suitable for automatic startup of nuclear power plant, which is based on the characteristics of typical PWR nuclear power plant unit system, operation management process and control requirements of automatic startup. Based on the analysis of the applicable control range, operation breakpoints, sequence control and analog control of the automatic start-up control system of PWR, an architecture for the automatic start-up control system of nuclear power plant is established, including the architecture design, the functions and design contents of each level and the interactive interface design between levels. At the same time, a typical PWR nuclear power plant automatic start-up simulation platform is established, and the automatic start-up control system is designed by taking the start-up process of nuclear power plant operation mode Ⅲ as an example, and the proposed technical scheme is simulated and verified. The simulation results show that the automatic start-up control system design can realize the automatic start-up of nuclear power plant mode Ⅲ, reducing the operation steps and workload of operators. The designed automatic start-up control system architecture in this study can provide a reference for the application of automatic start-up control system for nuclear power plant, and is of great significance for improving the automation level of start-up process of nuclear power plant units.
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Key words:
- PWR /
- Automatic start-up /
- Sequence control /
- Control system architecture
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表 1 压水堆核电厂运行模式表
Table 1. Operating Modes of PWR Nuclear Power Plants
运行模式 标准运行工况 实际功率/%FP 模式Ⅰ:
功率运行模式功率运行工况 2≤ 热备用 <2 反应堆临界阶段 ~0 模式Ⅱ:
SG冷却正常停堆模式热停堆工况 0 双相中间停堆工况蒸汽发生器冷却 0 双相中间停堆工况(RHR隔离) 0 模式Ⅲ:
RHR冷却正常停堆模式双相中间停堆工况(RHR连接) 0 单相中间停堆工况 0 正常冷停堆工况 0 模式Ⅳ:
维修停堆模式一回路微开维修冷停堆工况 0 一回路打开维修冷停堆工况 0 模式Ⅴ:
换料停堆模式换料停堆工况 0 模式Ⅵ:
反应堆卸料模式所有核燃料都在厂房 0 FP—满功率。 表 2 压水堆核电厂模式Ⅲ启动任务划分表
Table 2. Breakpoints of Mode Ⅲ Operation for PWR Nuclear Power Plants
任务序号 任务名称 1 初始状态检查 2 退出超压保护 3 SG蒸汽侧操作 4 一回路升温及建立汽腔准备 5 稳压器汽腔成功建立 6 TFA相关操作 7 建立SG排污 8 设定TSA定值,并投入二回路相关辐射监测仪表 9 RHR隔离前准备 10 热负荷由RHR切换至SG 11 RHR信号检查以及行政隔离 12 升温升压准备 TSA—汽轮机旁路系统。 -
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