核供热堆小破口事故实验研究

Experiment study on small break LOCA of nuclear heating reactor

通过不同功率、不同破口尺寸核供热堆小破口汽相事故排放的实验,研究了自然循环中断过程中系统的安全性和循环流量的波动现象;实验结果对核供热堆的安全运行及验证小破口事故安全分析程序有重要意义.

By small break vapor phase accident emission experiment of nuclear heating reactor with different power and different crack size, studies system＇s security and undulation phenomenon during the natural circulation break. Experiment result is significant for safe operation of nuclear heating reactor and security analysis program to confirm small break LOCA.