船舶核动力装置一回路小破口失水事故处置规程研究  

Study on Disposition of Small-break Loss-of-coolant Accident in Marine Nuclear Power Plant

作　　者：王元[1] 王少明[1] 于雷[1] 

机构地区：[1]海军工程大学船舶与动力学院,武汉430033

出　　处：《船海工程》2008年第5期102-106,共5页Ship & Ocean Engineering

摘　　要：利用建模仿真的方法,对船舶核动力装置一回路系统发生无法隔离的小破口失水事故进行研究。结果表明,只要采用正确的运行方案,可以在保证主冷却剂泵不受汽蚀影响的条件下,利用主冷却剂泵的低速运行,排出衰变热,使系统压力较快地降低到低压安全注射系统投入运行的压力,有效地保证反应堆安全。By using the real-time simulation,the un-separated SBLOCA（small-break loss-of-coolant accident） which occurred in primary loop circuit system of a marine nuclear power plant was studied.The research results showed that as long as the operating instruction is correct,the core decay heat can be removed under the main coolant pump＇s low speed running,and system pressure will depress quickly to a certain value while low pressure injection system is put into running.And in the whole progress,the main coolant pump should not be damaged by cavitation.The reactor will be safe.

关 键 词：核动力装置 小破口失水事故 主冷却剂泵 

分 类 号：TL364.4[核科学技术—核技术及应用]