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小堆小破口失水事故处理准则研究

Research on Operation Criteria of Small Break Loss of Coolant Accident for Small Modular Reactor

作者:杨庆明
  • 学号
    2015******
  • 学位
    硕士
  • 答辩日期
    2020.07.09
  • 导师
    李君利
  • 学科名
    核能与核技术工程
  • 页码
    60
  • 保密级别
    公开
  • 培养单位
    032 工物系
  • 中文关键词
    小堆,非能动,事故处理规程,小破口失水事故,事故分析
  • 英文关键词
    small modular reactor, passive system, emergency operating procedure, small break loss of coolant accident, accident analysis

摘要

由于具有高固有安全性、反应堆紧凑布置和系统简化等优点,模块化小型堆是未来核电多样性发展的一种重要核能新技术。ACP100小堆采用一体化、模块化技术,将蒸汽发生器(直流)内置于压力容器,取消了主回路的主管道,消除了大破口失水(大LOCA)事故,降低了堆芯发生熔化的几率,其非能动安全的典型特性显著提高了反应堆安全性。基于这些创新设计,小堆需要研究开发与小堆设计特征、事故自动及非能动响应相适应的事故处理规程技术。本文针对小堆事故处理规程开发研究,调研了当前的事故处理规程技术,总结提出了小堆事故处理规程技术的总体方法,包括征兆参数和状态功能等概念,总结提出了事故分析、事故处理策略分析和事故规程设计等技术分析步骤。进而,根据小堆的一体化反应堆设计、非能动系统设计特征,基于RELAP5/MOD3程序和小破口失水事故的事故分析模型,对典型小破口失水事故——DVI 10mm小破口和DVI 25mm小破口两个事故进行详细计算分析,研究各事故现象和过程。在详细事故分析的基础上,结合反应堆保护系统和安全系统的自动响应以及核电厂事故运行要求,研究了两种小破口事故工况下的运行现象、自动动作和手动干预必要性,提出并验证了小破口失水事故的重要处理准则,包括征兆信号、重要操作、操纵员干预时间窗口、关键定值等内容,为制定小堆小破口事故处理规程提供了技术基础和设计依据。

Small Modular Reactor is an important technology among nuclear power technology, due to its advantages of high intrinsic safety, compact reactor layout and simplified system compositions. As a Small Modular Reactor, ACP100 incorporates advanced integrated reactor technology and modular technology. It uses new technology to embed steam generators within reactor vessel, to cancel the primary pipes, eliminate large break LOCA, and decrease the probability of core melt. And together with the new design, its passive safety features largely improve the intrinsic safety of the ACP100 reactor system. Along with these new technologies, the emergency operating procedures shall be developed in the way to adapt the automatic and passive response features of ACP100.In the paper, the present emergency operating procedures technologies are investigated, and the general methodology of emergency operating is proposed to development of ACP100 emergency operating procedures, including the concept of symptom parameter, state function. And the necessary development process such accident analysis, operating strategy analysis and procedure design are raised.Based on the small break LOCA accident analysis model by RELAP5/MOD3 code in which the features of ACP100 integrated reactor and passive safety systems are analyzed and modeled, the two typical small LOCAs, i.e. DVI 10mm break and DVI 25mm break are analyzed, to investigate their phenomena and process.After the detail accident analyses, taking into account the emergency operation requirement and the automatic response of the protection and safety systems, the operation method and operator intervention are analyzed, and several key operation criteria are finally provided and validated, including the symptom signals, important actions, operator time windows, and critical setpoints. These provisions can be used as technical bases for ACP100 emergency operating procedures design.