Preliminary Assessment of Mean Steam Line Break Accident in an Integral Pressurized Water Reactor(IPWR)

In this paper, the research focuses on the safety evaluation of Integral Pressurized Water Reactor (IPWR) by taken into account the assessment of Mean Steam Line Break Accident(MSLB). In the current research the reactor under study is Inherent Safe Uranium Zirconium Hydride Nuclear Power Reactor INSURE-100 that has the power output of 100 MW.In this paper, first the reactor is describe in detail then nodalization diagram of the reactor is considered in order to simulate in thermal hydraulic system code Relap5/Mod3.4 with possible series of events under accident have been considered. The graphs obtained from the Relap5 code gives good preliminary assessment of the reactor under MSLB. In this paper time sequence of events with the graphical explanation have been depicted and are explained in detail.