Abstract
In this paper, a research has been carried out on the normal operational state of IPWR by using the thermal hydraulic system code Relap5/Mod3.4.In this study the conceptual study analysis of the reactor named as Inherent Safe Uranium Zirconium Hydride Nuclear Power Reactor INSURE-100 is considered but is only based on the conceptual study so the current research focuses on the normal operational of the reactor by using the Relap5/Mod3.4 code. For this purpose, two passive safety methods have been included for the safe operation as well as for transient analysis of the reactor. In the first one, Passive Residual Heat Removal System (PRHRS) has been modeled by taking the heat exchanger out of the Reactor Pressure Vessel (RPV) in the water tank so that it can absorb core decay heat in case of transient conditions and in the second one heat exchanger is placed both in inside and outside the RPV so that there can be another way to absorb the core residual heat. Considering these concepts figured out the normal operational state of the reactor by using Relap5/Mod3.4 in comparison with the conceptual design study of the reactor under consideration and the results extracted can be a good agreement for the transient analysis of the reactor.
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