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All Journal Ganendra: Majalah IPTEK Nuklir Jurnal Sains dan Teknologi Computational and Experimental Research in Materials and Renewable Energy (CERiMRE) Indonesian Journal of Physics (IJP) Jurnal Sains Materi Indonesia
Mustari, Asril Pramutadi Andi
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Astronomy Computer Science & IT Earth & Planetary Sciences Education Electrical & Electronics Engineering Energy Engineering Industrial & Manufacturing Engineering Materials Science & Nanotechnology Physics Other

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Comparison of Melted Corium Relocation during Severe Accident of High Temperature Reactor using Moving Particle Semi-Implicit Method Irfan, Muhamad; Humolungo, Ismail; Mustari, Asril Pramutadi Andi; Permana, Sidik
Computational And Experimental Research In Materials And Renewable Energy Vol 6 No 1 (2023): May
Publisher : Physics Department, Faculty of Mathematics and Natural Sciences, University of Jember

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.19184/cerimre.v6i1.39363

Abstract

System failure in nuclear reactors can cause degradation of a reactor core, allowing melting and relocation of the corium to the lower plenum in the nuclear reactor system. In this study, a severe accident simulation was carried out using the Moving Particle Semi-Implicit (MPS) method. In this method, we model the relocation of molten corium on the reactor core (support plate) to the lower plenum for several conditions with variations: corium material, lower plenum conditions, temperature, viscosity, and density. Those treatments were carried out in order to be able to compare and analyze the characteristics of the corium melt by reviewing the velocity profiles. The formation of a corium pool and debris bed can result in significant temperature differences and high heat flux against the walls of the reactor vessel, causing a decrease in the integrity of the reactor vessel and reactor failure.Keywords: Corium, Uranium Dioxide (UO2), Zirconium Dioxide (ZrO2), Fluid Relocation, Moving Particle Semi-Implicit (MPS).
MPS SIMULATION ON THE CORIUM MELT FLOW IN CASE OF REACTOR ACCIDENT Tursinah, Rasito; Variastuti, Marisa; Omega, Rakotovao Lovanantenaina; Mustari, Asril Pramutadi Andi; Permana, Sidik
GANENDRA Majalah IPTEK Nuklir Volume 26 Nomor 2, 2023
Publisher : Website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/gnd.2023.6829

Abstract

A simulation model has been made for molten corium in a nuclear reactor using the Moving Particle Semi-Implicit (MPS) method. By setting the value of dynamic viscosity and temperature of corium, simulations are carried out to display the pressure profile and flow velocity of the corium fluid that falls from the RPV to the plenum. In the first simulation to observe the pressure and velocity profile of the corium in the plenum, three conditions were made: the plenum was empty; the plenum was filled with corium fluid, and the plenum was filled with debris. The second simulation was carried out to determine the relationship between the time required for corium to reach the plenum for variations in corium viscosity and temperature values. The simulation results show that the increase in corium viscosity will be proportional to the length of time it takes to reach the plenum. In contrast to the effect of temperature where the increase in corium temperature will be the smaller the time required.
Simulation Of Mechanical Stress On A Solution-Annealed 15-15Ti Steel Using ABAQUS CAE Program Oktavianto, Putra; Purwaningsih, Anik; Setiawan, Muksin Aji; Handayani, Airin Hijrah; Mustari, Asril Pramutadi Andi; Waris, Abdul
Jurnal Sains Materi Indonesia Vol. 26 No. 1 (2024): Jurnal Sains dan Materi Indonesia
Publisher : BRIN Publishing (Penerbit BRIN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/jsmi.2024.3800

Abstract

In addressing the problem of Ti steel (15-15Ti) proposed as the main candidate material for the manufacture of coatings and fuel wrappers for liquid LBE-cooled fast reactors at high temperatures related to material degradation, such as liquid metal embrittlement (LME) and liquid metal corrosion (LMC), Gong et al. conducted research related to the creep failure behavior of solution-annealed 15-15Ti steel exposed to LBE at temperatures of 550 and 600oC using a creep test facility. However, in this study, testing the mechanical properties of 15-15Ti steel through tensile testing was not really discussed, even though the mechanical properties of a material are one of the most important things in determining structural design. The mechanical properties obtained from previous research were then simulated using ABAQUS CAE software to determine the stress distribution profile (initial and final) and the mechanical stress-strain performance used to understand more about the 15–15Ti material. From the simulation results, it was found that the peak force received by the specimen for a strain rate of 1.1 x 10-5s-1 was 6.0 kN, while for a strain rate of 5 x 10-5s-1, it was 6.2 kN. This means that the specimen used cannot accept a force greater than the peak force value. A stress-strain difference graph was also obtained in the experimental results, with simulation results showing a decrease in the value of the fracture point. This is because the mesh setting in the simulation is not close to a more detailed value.
Material Challenges for Corrosive Environments and High Temperatures in Lead-Cooled Fast Reactor Janah, Yulia Miftah Hul; Angelina, Tsania Eksa; Mustari, Asril Pramutadi Andi
Indonesian Journal of Physics Vol 35 No 2 (2024): Vol 35 No 2 2024
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.5614/itb.ijp.2024.35.2.3

Abstract

Research on one of the generation IV reactors, the Lead-Cooled Fast Reactor (LFR), began in the 1950s. The development of this reactor continues until now. However, there are material challenges in the development of LFR. LFR coolant that uses liquid Pb or Pb-Bi is one of the challenges in this reactor because it causes severe corrosion. Researchers have tested various materials such as steel, ceramics, composites, and refractory alloys in liquid Pb or Pb-Bi environments to assess their corrosion resistance. These materials have shown improved radiation performance at high temperatures and have been developed (such as ODS, FeCrAl, SS316, AISI 316 EP823, AISI 304, and HCM12A). However, these materials are not yet sufficiently compatible with corrosion performance. The results indicate that no metal or ceramic material currently proves to be completely resistant to corrosion and radiation over the long term. The LFR system is intriguing but has limited applicability until suitable construction material designs are further identified.
Simulation of Three Points Bending SS316 to Know Mechanical Stress with ABAQUS Janah, Yulia Miftah Hul; Mustari, Asril Pramutadi Andi
Indonesian Journal of Physics Vol 35 No 2 (2024): Vol 35 No 2 2024
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.5614/itb.ijp.2024.35.2.1

Abstract

The operating life of the Gen IV nuclear reactor, which is 60 years, will require material upgrades over a very long period of time. Stability, high reliability, adequate resources, and easy fabrication, as well as weldability, environmental impact, and aging, are other important aspects to consider during the material selection process. SS316 is currently in demand as a structural material for future Gen IV nuclear power plants operating at high temperatures. Although grade SS316 has been studied for current nuclear service conditions and other conventional applications, better data and models for long-term high-temperature properties are needed, especially with regard to primary to tertiary creep strain and creep-fatigue response. The three-point bending test on SS316 material can be modeled with ABAQUS simulation. The purpose of this study is to compare the distribution of the voltage profile for parameters at room temperature (25°C) and high temperature (650°C). In addition, simulations were conducted to compare the effects of load displacement (U2) variations, namely 25, 20 and 15 for each temperature. ABAQUS is an engineering simulation program based on finite element methods that can solve simple linear analysis problems to complex nonlinear simulations. ABAQUS comes with a comprehensive database of elements that can model almost any geometry. This simulation can describe the voltage profile that is spread over the geometry after the required parameters are entered. From the results obtained, the greater the displacement of U2, the smaller the maximum stress that can be resisted by the material. It also shows that at higher temperatures (650°C), materials tend to experience a decrease in strength or maximum stress compared to lower temperatures (25°C). So the material under test experiences a decrease in maximum strength or stress as the temperature increases and the U2 displacement.
Penerapan Metode Moving Particle Semi-Implicit dalam Simulasi Pelelehan Freeze Plug pada Molten Salt Reactor saat Terjadi Kecelakaan Reaktor Nurhajjah, Wafiq Azizah; Mustari, Asril Pramutadi Andi; Yulianto, Yacobus
JST (Jurnal Sains dan Teknologi) Vol. 12 No. 3 (2023): Oktober
Publisher : Universitas Pendidikan Ganesha

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23887/jstundiksha.v12i3.51634

Abstract

Sisi keamanan merupakan aspek yang sangat diperhatikan dalam mendesain suatu reaktor. Perpindahan panas yang cepat dalam pelelehan freeze plug merupakan salah satu faktor yang sangat krusial dalam desain reaktor molten molten salt. Tujuan penelitian ini adalah menganalisis perpindahan panas pada pencairan frozen salt dalam reaktor molten salt, mengevaluasi efektivitas desain freeze plug dengan dan tanpa logam tambahan (tembaga, kuningan, dan aluminium), serta memberikan rekomendasi desain untuk meningkatkan efisiensi dan keamanan reaktor molten salt. Penelitian ini merupakan penelitian kuantitatif dimana mekanisme perpindahan panas pada pencairan frozen salt disimulasikan dengan menggunakan metode Moving Particle Semi-Implicit dengan analisis 2D dengan menggunakan dua variasi desain. Desain yang disimulasikan adalah freeze plug dengan dan tanpa tambahan logam. Subjek penelitian utama dalam simulasi ini adalah freeze plug dalam reaktor molten salt. Simulasi tanpa tambahan logam dilakukan selama 250 detik. Pada desain dengan tambahan logam, digunakan tiga jenis logam, yaitu tembaga, kuningan, dan aluminium. Simulasi dengan tambahan logam dilakukan selama 25 detik. Hasil yang diperoleh menunjukkan bahwa desain dengan logam tambahan menghantarkan panas lebih baik daripada tanpa logam tambahan. Dari tiga logam tersebut, tembaga memiliki waktu paling cepat dalam mencairkan frozen salt. Hal ini menunjukkan bahwa semakin tinggi nilai konduktivitas termal suatu bahan, semakin cepat perpindahan panas ke freeze plug sehingga semakin cepat pelelehan freeze plug.
Co-Authors Abdul Waris Angelina, Tsania Eksa Handayani, Airin Hijrah Humolungo, Ismail Irfan, Muhamad Janah, Yulia Miftah Hul Nurhajjah, Wafiq Azizah Oktavianto, Putra Omega, Rakotovao Lovanantenaina Purwaningsih, Anik Rasito Tursinah, Rasito Setiawan, Muksin Aji Sidik, Adi Permana Variastuti, Marisa Yulianto, Yacobus