船用堆断电事故仿真及源项滞留分析  

Simulation of Ship Blackout for Ship Reactor and Analysis of Source Term Retaining

作　　者：晏峰[1] 陈力生[1] 张帆[1] YAN Feng;CHEN Li-sheng;ZHANG Fan(Dept.of Nuclear Energy Science and Engineering,Naval Univ.of Engineering,Wuhan,Hubei Prov.430033,China)

机构地区：[1]海军工程大学核能科学与工程系,湖北武汉430033

出　　处：《核科学与工程》2018年第2期256-262,共7页Nuclear Science and Engineering

基　　金：国家自然科学基金资助项目(11075212)

摘　　要：以某船用压水堆为研究对象,借助MELCOR程序建立事故分析模型,对全船断电事故进程进行仿真;对事故源项进行计算。结果表明:若应急电源无法投入,将导致堆芯熔化、支撑结构失效、舱底熔穿;大部分放射性物质排出舷外,稳压器及波动管滞留量次之,回路滞留量最少;各放射性核素在系统中滞留量也不相同,惰性气体滞留比例最小,仅为0.338 2%;卤素滞留量也相对较小,为3.848%;其余核素滞留比例都较高。本文研究结果可为进一步事故缓解研究及船外应急研究提供依据。Using MELCOR program,the accident analysis model was established for a new ship pressurized water reactor,simulating the whole ship blackout accident,calculating the source term of the accident.The study indicates that if the emergency power can’t be put into,it will lead to the core being melting,the core support being failing,the ship’s bottom being penetrating.Most of the radioactive material discharges overboard,the less lies in the pressurizer and the surge line,the least in the loops.The amount of different radionuclide is different,the inert gas is the least,only 0.338 2%,the halogen is also less,only 3.848%,the others are more.The research result can support the accident mitigation and decision of the nuclear emergency.

关 键 词：船用堆 MELCOR 全船断电事故 仿真 滞留量 

分 类 号：TL36[核科学技术—核技术及应用]