摘要
本文针对压力管式钍基先进核能系统(TANES)提出了一种非能动余热排出(PRHR)系统方案。该方案利用两个回路的自然循环,将事故工况下的堆芯余热排出到最终热阱。利用RETRAN02程序,以全厂断电事故为设计基准事故,对TANES非能动余热排出系统的余热排出能力进行了计算。计算表明,TANES的PRHR系统能够将余热导向最终热阱并且保持冷却剂回路和慢化剂回路的压力低于设计限值。另外对诸如设备间高度差等因素进行了敏感性分析。
This paper presents conceptual design for a passive residual heat removal (PRHR) system of the pressure tube water reactor (PTWR) that is called thorium-based advanced nuclear energy system (TANES) as well. The passive PRHR system includes two nature circulation loops to transfer the reactor residual heat to the heat sink. The RETRAN02 code was used to calculate the ability of the passive PRHR system of TANES at the design-based accident of losing conventional and dependable electrical power under full power. The calculation gave the conclusion that the passive PRHR system can remove the reactor residual heat to the ultimate heat sink and keep the pressure of the coolant loop and the moderator loop less than the limitations. Some factors such as the elevation of the heat exchanger are also studied.
出处
《核技术》
CAS
CSCD
北大核心
2003年第7期523-526,共4页
Nuclear Techniques
关键词
压力管式反应堆
余热排出系统
非能动
自然循环
Pressure tube water reactor (PTWR), Residual heat removal system, Passive, Natural circulation