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Computational Fluid Dynamics for Irregular Pentagon Natural Circulation Loop
Rahmad Dahana Saputra (a), Sidik Permana (a,b*), Duwi Hariyanto (c), Syeilendra Pramuditya (a,b), Syaiful Bakhri (d)

(a)Nuclear Physics and Biophysics Research Division, Physics Department, Faculty of Mathematics and Natural Science, Bandung Institute of Technology, Jalan Ganesha 10 Bandung 40132, Indonesia
(b)Nuclear Science and Engineering Department, Faculty of Mathematics and Natural Science, Bandung Institute of Technology, Jalan Ganesha 10 Bandung 40132, Indonesia
(c) Industrial Technology Faculty, Institut Teknologi Sumatera, Jl. Terusan Ryacudu, Lampung, Indonesia
(d) Research Center for Nuclear Material and Radioactive Waste Technology (PRTBNLR), Research Organization for Nuclear Energy, National Research and Innovation Agency (BRIN), South Tangerang 15314, Indonesia
*psidik[at]itb.ac.id


Abstract

Electricity is an important needs for everyday life. Nuclear Reactor is a power plant that have low CO2 emission and the energy is available at any time. Generation IV nuclear reactor have a passive safety system that allow it to run without external power source or any human intervention. One of the design of generation IV nuclear reactor is Molten Salt Reactor (MSR) that have natural circulation as its passive safety system. A study of irregular pentagon natural circulation loop using water as its coolant has been done previously. In this study the natural circulation loop is simulated using ANSYS Fluent. A mesh independece study is done for obtaining mesh with accurate result but at effective computational cost. After that some flow parameters is obtained, namely cold leg temperature, hot leg temperature, and the flow Reynolds number with a value of 34.29 C, 39.93 C, and 86.8-132.6 respectively . Those parameters is compared to a reference study and an error less than 3.5% are obtained. Those result mean that this simulation model can be used for further study.

Keywords: Natural Circulation, Ansys Fluent, Pentagon Loop

Topic: Innovative Nuclear Energy Systems

Plain Format | Corresponding Author (Rahmad Dahana Saputra)

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