优先级驱动控制系统是核电厂安全级分散控制系统(Distributed Control System,DCS)的一个重要组成部分,其主要功能是在对来自不同安全等级的自动或手动命令进行优先级处理后,驱动专设安全设施及相关支持系统的泵、阀等驱动设备,从而完...优先级驱动控制系统是核电厂安全级分散控制系统(Distributed Control System,DCS)的一个重要组成部分,其主要功能是在对来自不同安全等级的自动或手动命令进行优先级处理后,驱动专设安全设施及相关支持系统的泵、阀等驱动设备,从而完成系统规定的安全功能。田湾核电站7、8号机组将采用VVER-1200堆型,并将首次采用基于FirmSys平台的安全级DCS。而FirmSys平台已有的系统方案无法适用于该堆型要求,需研究设计满足此堆型要求的优先级驱动控制方案。本文通过对相关设计标准的解读以及堆型的需求,提出了一种适用于VVER-1200堆型的安全级优先级驱动控制设计方案,主要包括优先级管理方案和驱动管理方案,同时将此方案与其他堆型的控制方案进行对比确定了方案的合理性。该方案已在实际工程项目中成功应用。展开更多
VVER-1200 (Water-Water Energetic Reactor) represents a significant advancement in nuclear power generation, emphasizing the continuous analysis and enhancement of safety systems for reliable operation. The proposed st...VVER-1200 (Water-Water Energetic Reactor) represents a significant advancement in nuclear power generation, emphasizing the continuous analysis and enhancement of safety systems for reliable operation. The proposed study focuses on simulating combined scenarios involving steam generator tube rupture (SGTR) and AC power loss using core algorithms and models within personal computer transient analyzer (PCTRAN). Reactor kinetic equations, thermal-hydraulic balance, and safety system models are discussed to elucidate their role in simulating SGTR and AC power loss. Safety criteria, boundaries and initial conditions are outlined to provide a comprehensive understanding of the simulation framework. The analysis delves into dynamic behavior of VVER-1200, placing emphasis on thermal-hydraulic implications, essential reactor parameters, and radiation monitoring to facilitate impact evaluation. Continuous monitoring and maintenance of safety systems are underscored to ensure stable core cooling, particularly during proposed transient conditions. Through meticulous analysis and comparison with established benchmarks, this study contributes to bolstering the safety and reliability of VVER-1200 reactors by identifying vulnerabilities, assessing mitigation strategies, and refining emergency response protocols. Practical implications of this study offer a crucial understanding of reactor behavior, safety system performance, and emergency response strategies, thereby improving safety, optimizing operational practices, and reducing risks in nuclear reactor accidents.展开更多
文摘优先级驱动控制系统是核电厂安全级分散控制系统(Distributed Control System,DCS)的一个重要组成部分,其主要功能是在对来自不同安全等级的自动或手动命令进行优先级处理后,驱动专设安全设施及相关支持系统的泵、阀等驱动设备,从而完成系统规定的安全功能。田湾核电站7、8号机组将采用VVER-1200堆型,并将首次采用基于FirmSys平台的安全级DCS。而FirmSys平台已有的系统方案无法适用于该堆型要求,需研究设计满足此堆型要求的优先级驱动控制方案。本文通过对相关设计标准的解读以及堆型的需求,提出了一种适用于VVER-1200堆型的安全级优先级驱动控制设计方案,主要包括优先级管理方案和驱动管理方案,同时将此方案与其他堆型的控制方案进行对比确定了方案的合理性。该方案已在实际工程项目中成功应用。
文摘VVER-1200 (Water-Water Energetic Reactor) represents a significant advancement in nuclear power generation, emphasizing the continuous analysis and enhancement of safety systems for reliable operation. The proposed study focuses on simulating combined scenarios involving steam generator tube rupture (SGTR) and AC power loss using core algorithms and models within personal computer transient analyzer (PCTRAN). Reactor kinetic equations, thermal-hydraulic balance, and safety system models are discussed to elucidate their role in simulating SGTR and AC power loss. Safety criteria, boundaries and initial conditions are outlined to provide a comprehensive understanding of the simulation framework. The analysis delves into dynamic behavior of VVER-1200, placing emphasis on thermal-hydraulic implications, essential reactor parameters, and radiation monitoring to facilitate impact evaluation. Continuous monitoring and maintenance of safety systems are underscored to ensure stable core cooling, particularly during proposed transient conditions. Through meticulous analysis and comparison with established benchmarks, this study contributes to bolstering the safety and reliability of VVER-1200 reactors by identifying vulnerabilities, assessing mitigation strategies, and refining emergency response protocols. Practical implications of this study offer a crucial understanding of reactor behavior, safety system performance, and emergency response strategies, thereby improving safety, optimizing operational practices, and reducing risks in nuclear reactor accidents.
