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All Journal JURNAL KIMIA SAINS DAN APLIKASI Ganendra: Majalah IPTEK Nuklir Jurnal Pengembangan Energi Nuklir Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Jurnal Sains dan Teknologi JMPM (Jurnal Material dan Proses Manufaktur) Science and Technology Indonesia Indonesian Journal of Chemistry Computational and Experimental Research in Materials and Renewable Energy (CERiMRE) Indonesian Journal of Physics (IJP) Purbawidya: Jurnal Penelitian dan Pengembangan Arkeologi Jurnal Sains Materi Indonesia Jurnal Aplikasi Fisika
Mustari, Asril Pramutadi Andi
Institut Teknologi Bandung
Religion Arts Humanities Astronomy Biochemistry, Genetics & Molecular Biology Chemical Engineering, Chemistry & Bioengineering Chemistry Computer Science & IT Decision Sciences, Operations Research & Management Earth & Planetary Sciences Education Electrical & Electronics Engineering Energy Engineering Environmental Science Industrial & Manufacturing Engineering Materials Science & Nanotechnology Mechanical Engineering Medicine & Pharmacology Physics Social Sciences Other

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High Temperature Oxidation Behavior of ODS Ferritic Stainless Steel Fe-16Cr-4Al-1Ni-0.4Y2O3 Wafda, Hakimul; Prajitno, Djoko Hadi; Basuki, Eddy Agus; Syafiq, Ahmad; Widiawati, Nina; Andi Mustari, Asril Pramutadi
Indonesian Journal of Chemistry Vol 24, No 5 (2024)
Publisher : Universitas Gadjah Mada

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.22146/ijc.95284

Abstract

This study investigates the isothermic oxidation behavior of the new ODS alloy Fe-16Cr-4Al-1Ni-0.4Y2O3 (% by weight) at 700, 800 and 900 °C, with exposure times of 5, 20, 50, and 100 h at each temperature. The purpose is to obtain new data on its high-temperature parabolic oxidation constant for assessing oxidation resistance. The methods used include isothermal oxidation testing, XRD, SEM-EDS characterization, and analysis of oxidation kinetics by monitoring changes in oxide thickness using microscopy and SEM-EDS. The oxide products formed on the sample surface are Fe2O3, Fe3O4, AlFe2O4, and (Fe,Cr)2O3. Al and Cr oxides are located under the dominant Fe oxide layer on the surface of the sample. The oxidation test results showed that the most protective sample was obtained at a temperature of 700 °C for 100 h with an oxide thickness of 263.99 μm. The kinetics analysis correlates strongly with the parabolic equation (R2 ≈ 1). The oxidation rate constants at temperatures of 700, 800, and 900 °C were 681.76, 2957.5, and 12300 μm2 h−1, respectively. The activation energy required by the oxidation reaction in this alloy is 136.5 kJ mol−1. This research enhances understanding and potential applications of the Fe-16Cr-4Al-1Ni-0.4Y2O3 alloy in high-temperature environments.
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.
Corrosion Behavior of Modified F/M Steel with Ti and Dispersed Oxides: Y2O3 and ZrO2 Under High Temperature in Static Liquid Lead Setyo Hadi, Dhimas; Wafda, Hakimul; Pramutadi Andi Mustari, Asril; Trisnawan, Veri; Widiawati, Nina; Miftasani, Fitria; Hadi Prajitno, Djoko
Science and Technology Indonesia Vol. 10 No. 3 (2025): July
Publisher : Research Center of Inorganic Materials and Coordination Complexes, FMIPA Universitas Sriwijaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26554/sti.2025.10.3.877-888

Abstract

This study investigates the corrosion resistance of Oxide Dispersion Strengthened (ODS) steel in a lead environment, which is crucial for Lead-Cooled Fast Reactors (LFR), a type of Generation IV nuclear reactor. To improve corrosion resistance, two types of oxides-yttrium oxide (Y2O3) and zirconium oxide (ZrO2)-were added individually and in combination to the ODS steel. The samples were synthesized via powder metallurgy and characterized using optical microscopy, X-ray diffraction (XRD), scanning electron microscopy with energy-dispersive X-ray spectroscopy (SEM-EDX), and Vickers hardness testing. Corrosion testing was conducted in static liquid lead at 550°C for 75 hours. The results showed that the addition of Y2O3 and ZrO2 significantly refines grain structure, increases hardness, and promotes the formation of stable, protective oxide layers. Particularly, the dual-oxide (Y2O3+ ZrO2) sample exhibited the most uniform and effective oxide barrier, indicating improved resistance to lead corrosion. These findings demonstrate that dual-oxide dispersion is a promising strategy for improving the durability of structural materials in LFR applications.
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.
Eksplorasi Dinamika Fluida FLiBe pada Reaktor Garam Cair: Studi Simulasi Pengosongan Tangki Bahan Bakar Menggunakan Metode Moving Particle Semi-Implicit Aziz Satrio; Asril Pramutadi Andi Mustari; Muhammad Rizqie Arbie; Ismail Saleh; Muhammad Abhil Ardani
Jurnal Aplikasi Fisika Vol. 21 No. 1 (2025): Februari 2025
Publisher : Jurusan Fisika Fakultas Matematika dan Ilmu Pengetahuan Alam Universitas Halu Oleo

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.62749/jaf.v21i1.p14-24

Abstract

Peningkatan protokol keselamatan di dalam reaktor nuklir merupakan akibat langsung dari insiden yang parah. Kemajuan teknologi reaktor yang menghasilkan energi nuklir yang menjanjikan dan canggih adalah penggunaan bahan bakar cair dalam Reaktor Garam Cair, yang membedakannya dengan reaktor lain. Dengan menggunakan kerangka kerja Semi-Implisit Partikel Bergerak, sebuah model dikembangkan dalam penelitian ini untuk menganalisis fitur hidrodinamika tangki drainase dalam sistem keselamatan reaktor nuklir. Level permukaan cairan setelah 25 detik adalah 0,2 m untuk air biasa dan 0,156 m untuk FLiBe. Selama waktu simulasi 25 detik, kecepatan air ringan berkurang dari 3,8 m/s menjadi 1,9 m/s dan kecepatan FLiBe berkurang dari 4,05 m/s menjadi 1,93 m/s. Serupa dengan hasil kecepatan, tekanan hidrostatik air ringan menurun dari 9216,9 Pa menjadi 1074,3 Pa dan tekanan hidrostatik FLiBe menurun dari 14298 Pa menjadi 1577,9 Pa. Hasil yang diperoleh menunjukkan koefisien debit masing-masing cairan antara 0.6 dan 0.8 di mana debitnya antara 0,10 m³/s dan 0,12 m³/s. Hasil yang diperoleh menunjukkan bahwa pola yang diamati pada penurunan level cairan serupa, meskipun cairan berbeda dalam hal densitas dan viskositas kinematik. Ketiga cairan menunjukkan pola yang sebanding selama jangka waktu yang diamati, yang mengindikasikan respons dinamis yang serupa. Kecepatan, tekanan hidrostatik, dan kehilangan tekanan cairan menurun seiring waktu. Penyelidikan ini tidak hanya berfokus pada proses transmisi panas. Di masa depan, mungkin akan menarik untuk memasukkan transportasi panas dalam perhitungan. Hal ini dapat mengarah pada penemuan informasi lebih lanjut tentang dinamika cairan di dalam tangki karena perpindahan panas mempengaruhinya selama proses pembuangan.
Investigasi Mekanisme Peleburan Freeze Plug dalam Reaktor Garam Cair: Wawasan dari Eksperimen Lilin Padat-Minyak Panas Ismail Saleh; Asril Pramutadi Andi Mustari; Muhammad Rizqie Arbie; Jirman; Muhammad Abhil Ardani
Jurnal Aplikasi Fisika Vol. 21 No. 1 (2025): Februari 2025
Publisher : Jurusan Fisika Fakultas Matematika dan Ilmu Pengetahuan Alam Universitas Halu Oleo

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.62749/jaf.v21i1.p35-43

Abstract

Peleburan sumbat beku adalah fitur keselamatan pasif utama dalam Reaktor Garam Cair (MSR), yang dirancang untuk diaktifkan ketika suhu melebihi ambang batas. Sumbat peleburan memungkinkan garam cair mengalir dan mencegah panas berlebih. Penelitian ini menyelidiki prinsip-prinsip pencairan sumbat beku melalui eksperimen yang disederhanakan dengan menggunakan lilin padat dan minyak goreng panas. Sampel lilin padat dengan volume 25 ml, 50 ml, dan 75 ml dipaparkan pada minyak panas 140°C dalam volume 50 ml. Pengamatan menunjukkan bahwa volume minyak yang lebih besar menghasilkan suhu puncak yang lebih tinggi dan laju pendinginan yang lebih lambat, konsisten dengan konsep massa termal. Volume yang lebih besar menahan panas lebih lama dan memindahkannya secara lebih efektif, menciptakan puncak suhu yang lebih luas dan bertindak sebagai reservoir termal yang stabil. Sebaliknya, volume minyak yang lebih kecil menunjukkan kehilangan panas yang lebih cepat karena massa termal yang terbatas. Hasil ini menyoroti peran massa termal dalam mempertahankan panas dan mengelola laju pendinginan, yang sangat penting untuk keselamatan reaktor. Volume minyak yang lebih besar kemungkinan meminimalkan efek isolasi, memfasilitasi perpindahan panas yang efektif. Perilaku ini secara langsung berdampak pada laju pemanasan awal dan stabilitas suhu jangka panjang, yang penting untuk kinerja sumbat beku. Studi ini menggarisbawahi perlunya mengoptimalkan bahan sumbat beku, dengan fokus pada titik leleh, konduktivitas termal, dan stabilitas di bawah berbagai beban termal. Perbaikan di bidang-bidang ini dapat meningkatkan retensi panas dan kinerja perubahan fasa, meningkatkan keselamatan dan efisiensi reaktor. Penelitian di masa depan harus mengeksplorasi bahan dan konfigurasi alternatif untuk menyempurnakan desain MSR, memastikan operasi yang lebih andal dan sistem reaktor yang lebih aman.
Development of Standard Test Specimens for Competency Improvement of Non-destructive Test (NDT) Personnel—Industrial Radiography Sutanto, Jepri; Iswanto, Iswanto; Sumirat, Iwan; Pramutadi Andi Mustari, Asril; Permana, Sidik
JMPM (Jurnal Material dan Proses Manufaktur) Vol. 9 No. 2 (2025): December
Publisher : Universitas Muhammadiyah Yogyakarta

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.18196/jmpm.v9i2.26290

Abstract

Test specimens made of low-carbon SS400 steel in the form of plates and pipes will be manufactured for use by certification and training institutions. Currently, test specimens in Indonesia are imported, resulting in higher operational costs. Therefore, the domestic fabrication of test specimens is conducted to address this issue and improve the competency of NDT personnel. Radiographic techniques are applied to evaluate defects and verify acceptance criteria. Plate specimens with a geometry of 350 mm x 200 mm and pipes with a diameter of 2 "(50.8 mm) were welded using SMAW (Shielded Metal Arc Welding). Radiographic examinations revealed porosity and incomplete penetration (IP) defects on the plate specimens and four types of weld discontinuities on the pipe specimens: porosity, IP, external undercut, and spatter. The resulting density follows the acceptance standard, namely 2.12 on the plates and 1.91 on the pipes. Future evaluation using digital radiography methods such as computed radiography (CR) and digital detector arrays (DDA) is required to align with current technological advancements.
Co-Authors Abdul Waris Abdul Waris Ahmad Syafiq Airin Hijrah Handayani Amir Baliana Andriyati Rahayu Angelina, Tsania Eksa Anik Purwaningsih Anni Nuril Hidayati Atiek Rostika Noviyanti Aziz Satrio Baliana Amir Basuki, Eddy Agus Djoko Hadi Prajitno Faris Kamal Islahi Hadi Prajitno, Djoko Handayani, Airin Hijrah Humolungo, Ismail Iksal Iksal Irfan, Muhamad Ismail Saleh Iswanto Iswanto Iwan Sumirat Janah, Yulia Miftah Hul Jirman Koji Morita Miftasani, Fitria Muhammad Abhil Ardani Muhammad Rizqie Arbie Muksin Aji Setiawan Nur Akbar Nur Asiah Aprianti Nurhajjah, Wafiq Azizah Oktavianto, Putra Omega, Rakotovao Lovanantenaina Purwaningsih, Anik Putra Oktavianto Rasito Tursinah, Rasito Rifqa Fikriya Rahasri Rindi Wulandari Setiawan, Muksin Aji Setyo Hadi, Dhimas Sidik, Adi Permana Sumiati Sumiati Sutanto Sutanto Sutanto, Jepri Trisnawan, Veri Variastuti, Marisa Wafda, Hakimul Widiawati, Nina Yacobus Yulianto Yulianto, Yacobus