超临界水冷堆专设安全系统设计方案

Design Scheme of Special Safety System for Supercritical-Water-Cooled Reactor

简要介绍超临界水冷堆(SCWR)的设计要求和专设安全系统的设计原则,对SCWR自动泄压系统(ADS)、高压补水箱(RMT)、非能动余热排出系统(ICS)、非能动安全壳冷却系统(PCCS)和重力驱动堆芯冷却系统(GDCS)的功能及设计方案进行了详细描述。选取失流事故对SCWR安全系统的运行进行分析,验证了上述专设安全系统的有效性。

This paper gives a brief description of the design requirement and design principle of Supercritical-Water-Cooled Reactor （SCWR） Nuclear Power Plant safety system, particularly describes the function and the system design scheme of the automatic depressing system （ADS）, high pressure feedwater tank （RMT）, passive residual heat removal system （ICS）, passive containment cooling system （PCCS） and gravity driving core cooling system （GDCS）. The operation of the safety system is analyzed after loss of feedwater flowrate accident, to verify the validity of the SCWR safety system described above.