船用核动力装置SBLOCA破口尺寸敏感性分析  

Sensitivity Analysis of Break Size of SBLOCA for MNPP

作　　者：邢晋[1] 赵新文[1] 陈玉清[1] 杨磊[1] 

机构地区：[1]海军工程大学核能科学与工程系,武汉430033

出　　处：《四川兵工学报》2015年第3期64-66,75,共4页Journal of Sichuan Ordnance

摘　　要：针对船用核动力装置,采用SCDAP/RELAP5最佳估算程序,研究小破口失水事故(SBLOCA)进程,分析破口尺寸对事故的影响;结果显示,破口尺寸的大小对SBLOCA事故进程和后果有较大的影响,破口较小时,依靠投入高压安注系统(HPSI)等缓解措施,能够保证反应堆的安全;破口较大时,由于一回路压力较高,低压安注系统(LPSI)无法投入,导致高压熔堆;鉴于不同尺寸破口SBLOCA进程存在较大差异,在对于压水堆小破口失水事故分析研究时,进行破口尺寸敏感性分析是十分必要的。The progress of small break loss of coolant accident （SBLOCA） in marine nuclear power plant（MNPP） was studied based on the best estimate computer code of SCDAP/RELAPS, and the effect ofbreak size on the accident was analyzed. The results show that break size has great influence on the pro-gress and consequence of SBLOCA. The reactor safety can be ensured in the lesser break size accident iftaking some effective measures, such as high pressure safety injection system （HPSI） coming into service.However, because of a high pressure in the primary coolant circuit which leads to the low pressure safetyinjection system （LPSI） out of work, SBLOCA with larger size break could lead to high-pressure core meltaccident. Since the progresses of SBLOCA with different break sizes have large differences, the sensitivityanalysis of the break size is necessary when researching the SBLOCA in PWR.

关 键 词：船用核动力装置 小破口失水事故 破口尺寸 敏感性分析 

分 类 号：TL364[核科学技术—核技术及应用]