Assessment of Input Parameters and Architecture of RDE Reactor Protection System

Abstract

The Experimental Power Reactor (RDE) is a High Temperature Gas Cooled Reactor (HTGR) with 10 MW thermal which is planned as the first nuclear power plant (NPP) in Indonesia. The purpose of RDE development for Indonesia is to become technology provider related to the provision of electrical energy and cogeneration and become superior in the region. The safety factor is the most important factor in the operation of nuclear reactor to maintain the safety of reactor, people and the environment. Reactor Protection System (RPS) is an instrumentation and control system that serves to ensure the safety of the operation of the reactor, which will perform the reactor trip automatically if the reactor operation exceeds the safety limits. The research of RDE RPS design aims to support the development activities of RDE detailed design especially in RPS design. This design is based on accidents already outlined in Design Basic Accident (DBA) and is designed with a level of reliability that meets the requirements. In order for RPS to function when demanded it is necessary to know the parameters of the process used for the detection of the occurrence of DBA. The purpose of this research is to identify the input parameters used by RPS especially at the initiating level. The results of the identification obtained are important in the development of RPS architecture. The research methodology was conducted with DBA scenario analysis listed in the RDE conceptual design document and RPS design review on HTGR in general.