首页> 中文期刊> 《核科学与工程》 >小破口引发的严重事故工况及事故缓解的研究

小破口引发的严重事故工况及事故缓解的研究

         

摘要

利用MAAP4程序对方家山核电站进行建模,针对事故后果较为严重的小破口事件进行了计算分析,得到了假设事故下电厂系统的反应以及相应的严重事故现象.对事故中发生的DCH(安全壳直接加热)现象和安全壳失效以及裂变产物向环境的释放进行了分析.随后,本文根据相关的严重事故管理导则和该事故的特点,对缓解该事故的策略进行了研究和计算分析.计算结果表明采取的事故缓解措施是有效可行的,从而为方家山及类似的三环路电厂严重事故的缓解提供了一种有效可行的策略.%Fangjiashan nuclear power plant is modeled, by using MAAP4 code. Base on this model, the small LOCA accident is calculated, which will cause the worst consequence. The response of the plant and relevant severe accident phenomena are obtained.The phenomena of DCH (direct containment heat) happened during the accident, containment failure and release of the fission production are analyzed. Then, according to the related severe accident management and characteristic of this accident, the strategy of mitigating the accident consequence is studied and calculated. The result indicated that the mitigation action is very efficient. Therefore, a feasible strategy of mitigating the severe accident consequence is provided for the three-loop plant like Fangjiashan in China.

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