摘要
针对ACPR1000反应堆,本文采用THEMIS程序和FLICAⅢ-F程序进行了热态满功率工况下主蒸汽管道破裂事故的破口谱分析,并且就最恶劣工况下的SG蒸汽流量、反应堆冷却剂入口温度、堆芯热功率、堆芯压力等关键参数的变化情况进行了介绍。结果如下:随着破口直径的减小,停堆时间逐渐推迟,当主蒸汽管道破口直径DN≤200 mm时,反应堆不触发停堆;当DN=300 mm、250 mm和230 mm时,反应堆由高中子注量率触发停堆;当DN=407 mm和350 mm时,反应堆由安注信号触发停堆。此外,从堆芯后果方面考虑,DNBR值随着破口尺寸的减小而先减小后增大,并且在DN=230 mm时达到最小值1.50,满足验收准则。
According to ACPR1000, this paper uses THEMIS ad FLICA Ⅲ-F to analyze the break spectrum of Main Steam Line Break accident under Hot Full Power condition. And it introduces key parameters of the worst condition with time, such as SG steam flow, reactor coolant inlet temperature, core thermal power, core pressure, etc. As the results show, with the decrease of the break diameter, the shutdown time is gradually delayed. When the break diameter DN ≤ 200 mm, the reactor will not shut down;When the DN=300 mm, 250 mm and 230 mm, the high neutron flux rate will trigger the reactor trip;When the DN=407 mm and 350 mm, the reactor will shut down by safety injection signal. In addition, for the core consequences, the DNBR value decreases first and then increases with the decrease of the break diameter, and reaches the minimum value at DN=230 mm, with a DNBR value of 1.50, which meets the acceptance criteria.
作者
林燕
罗汉炎
李强
张冠中
韩圳南
王雄
Lin Yan;Luo Hanyan;Li Qiang;Zhang Guanzhong;Han Zhennan;Wang Xiong(China Nuclear Power Technology Research Institute Co.Ltd,Shenzhen 518028,China)
出处
《核安全》
2022年第2期32-37,共6页
Nuclear Safety
作者简介
林燕(1995-),女,工程师,硕士,现主要从事核电厂的安全分析工作;通讯作者:罗汉炎,E-mail:luo.hanyan@cgnpc.com.cn。
