CHARACTERISTICS OF CERAMIC-BRICK HEATER (BCH) BLANKETS 02 FOR THE PASSIVE SYSTEM SIMULATION FACILITY (FASSIP) 01 MODIFICATION 1

  • Idznur Rizky Muhammad Universitas Riau

Abstract

Accidents that occurred at the Fukushima Daiichi nuclear power plant, led to research throughout the world including Indonesia. One solution is to make a passive cooling system in a nuclear reactor. The working principle of this passive cooling system is with closed loop natural circulation using differences in density. At high temperatures, the density will decrease causing the working fluid which has a high temperature to rise to the top, then it will be cooled by a cooling device on the system. With this working principle, research and development of reactor safety systems was carried out at PTKRN BATAN. The research facilities that have been built are called FASSIP (Utility of Passive System Simulation) 01 Mod.1. There are several components of FASSIP 01 Mod.1, namely heating components using a heating system using ceramic-brick heater (BCH) 02 and refrigeration components with the system of cooling cooling system (RCS). Therefore, BCH-02 is tested to determine the temperature distribution characteristics in the BCH-02 section. Based on the results of experiments carried out for 105 minutes, the temperature distribution on BCH 02 the greater the power given, causing the temperature to be higher. The temperature on the ceramic-brick surface is higher than in the section pipe, this is due to heat loss before reaching the section pipe.

Keywords: Fukushima Daiichi, nuclear reactor, FASSIP 01 Mod.1, BCH-02, ceramic-brick

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Published
2019-04-01
How to Cite
Muhammad, I. (2019). CHARACTERISTICS OF CERAMIC-BRICK HEATER (BCH) BLANKETS 02 FOR THE PASSIVE SYSTEM SIMULATION FACILITY (FASSIP) 01 MODIFICATION 1. Machine : Jurnal Teknik Mesin, 5(1), 15-20. https://doi.org/10.33019/jm.v5i2.770
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