Simulasi Pelelehan Freeze Plug Termodifikasi pada Molten Salt Reactor Menggunakan Metode Moving Particle Semi-implicit

Authors

  • Banafsaj Fatiya Nabiilah Institut Teknologi Bandung
  • Asril Pramutadi Andi Mustarib ITB
  • Yacobus Yulianto

DOI:

https://doi.org/10.26418/positron.v12i2.57434

Keywords:

freeze plug, frozen salt, MPS, MSR

Abstract

In the Molten Salt Reactor, the freeze plug is one of the components that plays an important role when a reactor accident occurs. In designing the freeze plug, the selection of the constituent material is based on the ability of the material to spread the heat. Therefore, studies on material selection are needed to provide information regarding freeze plug design. The modified freeze plug melting process has been simulated using the Moving Particle Semi-Implicit method. This study aims to observe the behavior of the modified freeze plug melting phenomena and to see the effect of the conductivity value on the melting process. The alloys used around frozen salts with different thermal conductivity are Hastelloy-N, Heynes-242, and ODS Alloy (MA754). The simulation results show that the time required for frozen salt to melt in Hastelloy-N, Heynes-242 variations , and ODS Alloy (MA754) are 12.3 seconds each; 12.7 seconds; and 24.3 seconds. The results obtained explain that freeze plugs with metal alloys that have the highest thermal conductivity require a shorter time to reach the melting point. This shows that the greater the thermal conductivity value, the easier it is to spread heat to the alloy that hits the frozen salt.

References

Fukushima accident, https://www.britannica. com/event/Fukushima-accident (accessed Jul 18, 2022).

Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety - The Accident at TEPCO’s Fukushima Nuclear Power Stations -, https://japan.kantei.go.jp/ kan/topics/201106/iaea_houkokusho_e.html (accessed Jul 18, 2022).

Buckthorpe, D. Introduction to Generation IV nuclear reactors. Structural Materials for Generation IV Nuclear Reactors. , 1–22. (2017).

Zohuri, B. Generation IV nuclear reactors. Nuclear Reactor Technology Development and Utilization. , 213–246. (2020).

IAEA , Advances in Small Modular Reactor Technology developments, A Supplement to: IAEA Advanced Reactors Information System (ARIS) 2020 Edition, pp.354, 2020.

ARIS-IAEA , ThorCon ( Thorcon US , Inc .) USA / Indonesia2020.

Allibert, M. , Merle, E. , Delpech, S. , Gerardin, D. , Heuer, D. , Laureau, A. , dan Moreau, S. , Preliminary proliferation study of the molten salt fast reactor, EPJ Nuclear Sciences & Technologies, 6pp.5, 2020.

Yanti, N. J. , Mustari, A. P. A. , Hidayati, A. N. , dan Aprianti, N. A. , The effect of Copper utilization on MSFR’s safety plug performance simulation by using MPS, Journal of Physics: Conference Series, 2243(1), pp.012059, 2022.

Hidayati, A. N. , Waris, A. , Mustari, A. P. A. , Irwanto, D. , dan Aprianti, N. A. , Moving particle semi-implicit simulation on the molten Wood’s metal downward relocation process, Nuclear Science and Techniques, 32(8), pp.1–12, 2021.

Hidayati, A. N. , Waris, A. , Andi Mustari, A. P. , Apriani, N. A. , Ifthacharo, M. , dan Wulandari, R. , The Effect of Temperature Variations on Wood’s Metal Plate Melting Simulation by Using MPS, Journal of Physics: Conference Series, 1493(1), pp.0–7, 2020.

Mustari, A. P. A. , Iksal , Sumiati , Syeilendra , Irwanto, D. , dan Aprianti, N. A. , Prediction of Melting Penetration of Armco Iron by Liquid Uranium Using MPS_LER, Journal of Physics: Conference Series, 755(1), 2017.

Hidayati, A. N. , Mustari, A. P. A. , Waris, A. , Yulianto, Y. , dan Ilham, M. , Study on Fluid Descends Vertically on Static Fluid Using Moving Particle Semi-Implicit Method, Journal of Physics: Conference Series, 1772(1), 2021.

Koshizuka, S. dan Oka, Y. , Moving-particle semi-implicit method for fragmentation of incompressible fluid, Nuclear Science and Engineering, 123(3), pp.421–434, 1996.

Tuyll, F. Van , A new design for the safety plug in a Molten Salt Fast Reactorpp.47, 2016.

Ignatiev, V. , Feynberg, O. , Merzlyakov, A. , Surenkov, A. , Zagnitko, A. , Afonichkin, V. , Bovet, A. , Khokhlov, V. , Subbotin, V. , Fazilov, R. , Gordeev, M. , Panov, A. , dan Toropov, A. , Progress in development of MOSART concept with Th support, International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, 2(January), pp.943–952, 2012.

MatWeb: Online Materials Information Resource, https://www.matweb.com/

Wright, R. N. dan Sham, T.-L. , Status of Metallic Structural Materials for Molten Salt Reactors, INL/EXT-18-45171 Revision 0, INL/EXT-18-45171, Argonne National Laboratory, (May), pp.INL/EXT-18-45171, Argonne Natl. Lab., 2018.

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Published

2022-11-30

Issue

Vol. 12 No. 2 (2022): Vol. 12 No. 2 Edition

Section

Articles

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