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在核反应堆假想的破口事故下,破口处可能因急剧降压和汽化而形成临界流动,此时的流动特性对事故的进程和堆芯冷却剂装量有较大影响,从而对元件的温度有显著影响。为此,本研究在较高的压力范围内进行临界流稳态实验,认识临界流现象的基本特性和参数影响趋势,积累试验数据,为COSINE软件的开发和验证提供试验
Under the hypothetical breaking accident of nuclear reactor, the breaking point may form a critical flow due to the sharp depressurization and vaporization. At this time, the flow characteristics have a great influence on the progress of the accident and the loading capacity of the core coolant, so the temperature of the component Have a significant impact. Therefore, in this study, the critical flow steady-state experiments were carried out in a relatively high pressure range, and the basic characteristics of critical flow phenomena and trend of the parameters were recognized, and the experimental data were accumulated to provide a test for the development and verification of COSINE software