船用堆严重事故下熔融物堆内滞留能力分析  

Analysis of In-Vessel Retention Capacity for Marine Reactor Severe Accident

作　　者：何翼麟 张帆[1] 张杨伟[1] He Yilin;Zhang Fan;Zhang Yangwei(Department of Nuclear Energy Science and Engineering,Naval University of Engineering,Wuhan,430033 China)

机构地区：[1]海军工程大学核能科学与工程系,武汉430033

出　　处：《核动力工程》2018年第5期111-116,共6页Nuclear Power Engineering

摘　　要：堆芯熔化的严重事故,可能导致船用堆下封头失效、熔融物进入堆坑,危害人员及船体安全。本文采用严重事故一体化程序MAAP4,以船用堆全船断电事故为研究对象,针对低压安全注射系统投入时机、低压安全注射水流量,研究下腔室熔池形成后,投入低压安全注射系统对熔融物堆内滞留的作用。结果表明:在下腔室熔池形成后1576 s时,投入两台安全注射泵仍能有效阻止压力容器失效,实现熔融物堆内滞留;在下腔室熔池形成2646 s后,投入低压安全注射系统不能阻止压力容器失效。Reactor core melt down accident may result in lower head failure, and molten material may relocate into the cavity, which endangers the safety of personnel and hull. The severe accident integration calculation program called MAAP4 code is adopted to study the effects of low pressure injection systems launching time and flow rate when the corium pool had formed for In-Vessel retention. The results show that two low pressure injection pumps can effectively prevent the failure of pressure vessels and the corium melt can be retained within the reactor when the corium pool had been formed for 1576 s, the low pressure injection systems cannot prevent the pressure vessel failure 2646 s after the corium pool had been formed.

关 键 词：严重事故 熔池 压力容器失效 MAAP4程序 

分 类 号：TL364[核科学技术—核技术及应用]