Simulation of Loss of Coolant Accident in an Integral Pressurized Water Reactor (IPWR)
In this paper research has been carried out on the Loss of Coolant Accident (LOCA) in an Integral Pressurized Water Reactor(IPWR) by using thermal hydraulic system code Relap5/Mod3.4.The designing of Integrated Pressurized Water Reactor (IPWR) incorporates the safety and reliability of the reactor to withstand under accidental vulnerabilities.In this study,the reactor under consideration is Uranium Zirconium Hydride Nuclear Power Reactor INSURE-100 with the power output of l00MW.In the current research,the reactor has been described in detail according to the requirement for the simulation of LOCA using Relap5 code with the possibility of occurrence of the time sequence of events.The graphs obtained shows good agreement for the safe operation of IPWR under LOCA.
Integrated Pressurized Water Reactor (IPWR) Loss of Coolant Accident (LOCA) Relap5/Mod3.4 code Sequence of events Graphical explanation
Salah Ud-Din Khan Minjun Peng Muhammad Zubair
College of Nuclear Science and Technology, Harbin Engineering University 145-Nantong Street, Nan gang District, City Harbin, Heilongjiang Province.P.R.China
国际会议
重庆
英文
410-414
2011-06-23（万方平台首次上网日期，不代表论文的发表时间）