采用分离式热管的非能动安全壳冷却系统研究

Study on Passive Containment Cooling System Using Separated Heat Pipe

  • 摘要: 非能动安全壳冷却系统(PCCS)是第3代先进压水堆核电厂重要的专设安全系统。本文提出一套采用分离式热管技术的PCCS,通过原理性试验和系统性热工水力分析程序研究系统启动和稳态运行的流动和传热特性,研究影响系统运行及热传输能力的关键因素,验证系统设计的可行性。研究结果表明,该系统的传热性能随安全壳的状态变化有极强的自适应能力,在事故工况下利用该系统作为非能动的安全壳热量移出措施是可行、有效的。程序分析结果与试验结果及国际上已有研究成果的对比分析表明,RELAP5程序对于该系统热工水力分析是适用的。蒸发段传热管内流型、传热模式、空泡份额等关键流动、传热参数的变化表明,系统初始充液率对系统传热性能有重要影响。较小的冷热芯位差即能提供足够的自然循环驱动力,冷热芯位差不是系统布置的主要制约因素。

     

    Abstract: Passive containment cooling system (PCCS) is an important engineered safety feature in generation Ⅲ advanced pressurized water reactor. A PCCS using separated heat pipe technology was promoted. Flow and heat transfer characteristics during the system start-up and in steady state were studied by mechanism test and systematic thermal hydraulic analysis code. Key influencing factors on operation and heat removal capacity of the system were also discussed and feasibility of the system design was validated. The results show that the heat removal capacity of the system has strong self adaptability with containment conditions. The system is a feasible and effective approach to passively cool the containment in accident conditions. Comparisons between code analyses and the test and existing research results show that RELAP5 code is an applicable thermal-hydraulic analysis code for the system. Key flow and heat transfer parameters change in the vaporization heat transfer tube, such as flow regimes, heat transfer modes and void fractions, indicates that heat removal capacity of the system is significantly affected by initial fluid filling rate. Minor height difference between cold and hot cores is able to provide sufficient natural circulation driven force, and that is not an important restriction factor for the system arrangement.

     

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