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 100MW.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.
Ran Chen and Wenli Yao
S. U. D. Khan et al., "Simulation of Loss of Coolant Accident in an Integral Pressurized Water Reactor (IPWR)", Advanced Materials Research, Vols. 230-232, pp. 410-414, 2011