Numerical Simulation of the Effect of Molten Salt Channel Number on Temperature Distribution in Molten Salt Core Reactor
Amelya Dwiyulianti (a), Ahmad Yonanda (b), Zulfalina (c), Rini Safitri (c), Elin Yusibani (c*)

(a) Graduate Programs in Physics, Physics Department, FMIPA Universitas Syiah Kuala, Jl Teuku Nyak Arief Darussalam, Indonesia 23111
(b) Mechanical Engineering, Faculty of Engineering, Universitas Lampung. Jl. Prof. Dr. Ir. Sumantri Brojonegoro, Gedong Meneng, Kec. Rajabasa, Bandar Lampung, Indonesia 35141
(c) Physics Department, FMIPA Universitas Syiah Kuala, Jl Teuku Nyak Arief Darussalam, Indonesia 23111
*e_yusibani[at]usk.ac.id

Abstract

One important aspect in the design of a nuclear reactor that needs to be considered is thermal analysis. This parameter is closely related to the circulation of molten salt, which serves as a fuel and coolant in MSR reactors. This study simulates the temperature distribution performance of the MSR by considering the effect of the number of molten salt channels with inlet temperature variations. Knowing the temperature distribution will predict the characteristics of heat transfer in the form of natural convection for the survival of the reactor. The reactor design used in this study was MSBR developed by ORLN. ANSYS Fluent with 3D model was employed to investigate the system behavior under steady-state conditions. The geometry is divided into two regions, solid (graphite material) and fluid (molten salt). The thickness of the moderator and radius of the molten salt channel were 0.0508 and 0.0208 m, respectively. The moderator height was 1.98 m. The number of salt channels varied up to three. The results showed that there was a temperature difference of 11 to 14 K when the channel was increased from one to three channels.

Keywords: MSR, Fluent, temperature distribution, molten salt, graphite

Topic: Nuclear Science and Engineering