Simulation of nuclear steam supply system of experimental power reactor

Abstract

The Indonesia Nuclear Energy Agency (BATAN) has been being managed to design the so called Experimental Power Reactor (EPR), which is a High Temperature Gas Cooled Reactor (HTGR) type with the thermal power of 10 MW. The purpose of the reactor development is a safely demonstration of a small modular nuclear power plant operation. As part of the detail design document of EPR up to the year 2019, the capability to perform the operation based on the determined safety margin have to be described by simulation of the EPR model. The purpose of this work is to simulate the nuclear steam supply system (NSSS) of the EPR, which can demonstrate the steady-state operation performance of the EPR starting from the heat generation in the pebble bed core up to the steam generation in the steam generator component using the RELAP5. Therefore, a complete model of NSSS should consist of primary system and secondary system, which are connected by a piping component consisting of the cold and hot ducts installed in co-axialed way. The simulation of Nuclear Steam Supply System (NSSS) of EPR using RELAP5 results in the output data, which are in general lower than the EPR thermal design data for 100 % core power. For the 50 % core power, the results require further investigation, especially in the methodology of the simulation to achieve the steady-state condition for more representative output. For the 100 % core power, the model of the NSSS of EPR can be used for a selected transient event involving the secondary system.The Indonesia Nuclear Energy Agency (BATAN) has been being managed to design the so called Experimental Power Reactor (EPR), which is a High Temperature Gas Cooled Reactor (HTGR) type with the thermal power of 10 MW. The purpose of the reactor development is a safely demonstration of a small modular nuclear power plant operation. As part of the detail design document of EPR up to the year 2019, the capability to perform the operation based on the determined safety margin have to be described by simulation of the EPR model. The purpose of this work is to simulate the nuclear steam supply system (NSSS) of the EPR, which can demonstrate the steady-state operation performance of the EPR starting from the heat generation in the pebble bed core up to the steam generation in the steam generator component using the RELAP5. Therefore, a complete model of NSSS should consist of primary system and secondary system, which are connected by a piping component consisting of the cold and hot ducts installed in co-axialed...