Research

My current research projects comprise:

    1. Development of Floating Nuclear Power Plants
    2. Safety evaluation of LWR with accident-tolerant fuels
    3. Development of small modular reduced moderation LWR
    4. Development of HTR-based Microreactor
    5. Redesigning of a high-temperature gas-cooled fluidized bed nuclear reactor
    6. Metaheuristic Optimization
    7. Machine Learning

(Tersedia beberapa tema Tugas Akhir/skripsi, silakan klik pada research project di atas untuk melihat detail)

Past supervised students

  1. Subchannel Analysis on KLT-40S Reactor Fuel Assembly to Calculate the Distribution of Hydraulic Thermal Characteristics using RELAP5-3D, Agung Krisna Mukti, 2022.
  2. Heat Pipe Nuclear Micro Reactor Modelling Using Liquid Metal Coolant and U3Si2, Tanti Henditasari, 2022.
  3. Core Modelling of 7LiF-BeF2-Cooled High Temperature Nuclear Micro Reactor with UO2-ThO2 Fuel, Rahmatika Intan Ali, 2022.
  4. Steam Generator Tube Rupture Detection in the Pressurized Water Reactor using a Website-Based Expert System with Forward Chaining Method, Diyastri Khotimatul Huda, 2022.
  5. Neutronic Analysis of Burnable Poison Addition in a Small-PWR Fuel Assembly with QUADRISO Uranium Mononitride Fully Ceramic Micro-encapsulated Fuel, Bagaskara Eka Nugraha, 2021.
  6. Fuel Loading Pattern Optimization using Polar Bear Optimization Algorithm to Extend Reactor Operation Period, Shaffan Haqi, 2021.
  7. Coupled Monte Carlo Method and Discrete Element Method for Depletion Calculation of HTR-10, Feryantama Putra, 2021.
  8. Fuel Loading Pattern Optimization of Reactor Based on BEAVRS In Order To Minimize Power Peaking Factor with Reactor Operating Time Restriction using Polar Bear Optimization Algorithm, Amila Amatullah, 2021.
  9. The Effect of Adding a Cover to Water Cooling Tank of Small Modular Reactor to Thermal Performance of the Vertical Straight Wickless-Heat Pipe, Nur Fakhri Sholahuddin, 2021.
  10. Modelling and Criticality Analysis of Initial Phase Design of Experimental Power Reactor Core With the OpenMC Code, Wiesnu Ardy Aliefantoro, 2021.
  11. Improvement Performance Design of X-Ray Production System in Intraoral Dental Radiography Tube Based on MCNP Simulation, Fikra Laksana Putra, 2021.
  12. Analysis of Reflector Rod Reactivity Worth in a Heat Pipe Micro Reactor, Luqman Hasan Nahari, 2020
  13. Determination of Seed and Blanket Ratio and Temperature Reactivity Coefficient of Micro Reactor Heat Pipe, Hadi H. Nababan, 2020.
  14. Thermal Hydraulics Study on The Primary Loop of KLT-40S During RCP Coastdown, Faris Alkodri, 2020.
  15. Increase in Discharge Burnup and Reduction of Plutonium Production in an Integral Pressurized Water Reactor with Micro-heterogeneous Fuel, Benyamin Dariadi, 2019.
  16. Subchannel Analysis of AP-1000 Fuel Assembly to Determine the Minimum Departure from Nucleate Boiling Ratio (MDNBR) using RELAP5-3D, Adnan Wisudhaputra, 2019.
  17. In-Core Nuclear Fuel Management in an Integral Pressurized Water Reactor for Transuranic Waste Transmutation, Ezra Siekta Wibowo, 2019.
  18. Small Modular Reactor for Bangka Belitung Province Energy Planning using LEAP Software, Muhammad Adipurna Kusumawardana, 2019.
  19. Electrical Energy Supply Planning in East Kalimantan and North Kalimantan Province using IRIS Reactor, Rizka Mahendra, 2019.
  20. Core Design Optimization of Dual Fluid Molten Salt Reactor with UF4-LiF-ThF4fuel and ThF4-LiF4Blanket, Paksi Pratita Murti, 2019.
  21. Design of Analysis System of Process Imaging from Bone Scintigraphy as a Predictor for Validation of Bone Metastasis, Herlina Zainal, 2019.
  22. Thermalhydraulic Analysis of Integral Pressurized Water Reactor using MOX Fuel, Silvia Phungky, 2019.
  23. Neutronics Analysis of Proposed Modified Core Model Traveling Wave Reactor-Prototype, Sandy Sanjaya Awaludin, 2019.
  24. Neutronics and Thermal-hydraulics Assessment of Reduced Moderation Pressurized Water Reactor using Thorium Fuel, Martinus I Made Adrian Dwiputra, 2019. (Master Thesis)
  25. Analysis and Computational Validation of Core Excess Reactivity and Shutdown Margin of Kartini Reactor, Umar Sahiful Hidayat, 2019. (Master Thesis)
  26. Coupled Neutronics-Thermalhydraulics for Steady and Transient Pressure and Inlet Mass Flow Rate in KLT-40s Reactor using RELAP5-3D, Ade Chandra Lesmana, 2019.
  27. Modeling and Analysis on the Influence Leak Area in Main Steam Line Break Accident to Thermal-hydraulics Parameters of a Pressurized Water Reactor using RELAP5-3D, Mhd. Yusuf Hanafiah, 2019.
  28. Analysis on the Characteristics of Primary Fluid Flow and Heat Transfer in 10 MWt High Temperature Reactor – Test Module (HTR-10) during Steady and Transient using Fluent 6.3, Edward Steven Sembiring, 2018.
  29. Core Design Parameteric Study of Integral Pressurized Water Reactor (iPWR) with Mixed Oxide Ceramic Fuel using SRAC Code System [Studi Parameter Desain Teras Integral Pressurized Water Reactor (iPWR) dengan Bahan Bakar Keramik Campuran Oksida (Mixed Oxide Ceramic Fuel) Menggunakan Program SRAC, Harun Ardiansyah, 2018.
  30. Neutronic Conceptual Design Reactor “Indonesian Space Reactor (ISR)” as a Spacecraft Power Plant on Deep Space Exploration Mission using Monte Carlo Method [Desain Konseptual Neutronik Reaktor “Indonesian Space Reactor (ISR)” Sebagai Pembangkit Listrik Pesawat Ruang Angkasa pada Misi Deep Space Exploration Menggunakan Metode Monte Carlo], Muhammad Farid Khandaq, 2018.
  31. Small Break Loss-of-Coolant Accident Analysis for a 3-Loop PWR with Accident Tolerant Fuel (ATF) using RELAP5 [Analisis Kecelakaan Jenis Small Break Loss-of-Coolant Accident (SBLOCA) pada Pressurized Water Reactor (PWR) 3-Loop dengan Accident Tolerant Fuel (ATF) Menggunakan RELAP5, Fathurrahman Setiawan, 2018.
  32. Analysis of Motion Effect on KLT-40S Reactor Pressure Vessel in a Floating Craft due to Ocean Wave upon Thermal Hydraulics Characteristics of Reactor using RELAP5-3D [Analisis Pengaruh Gerakan pada Bejana Tekan Reaktor KLT-40S di dalam Wahana Terapung akibat Gelombang Laut terhadap Karakteristik Termal Hidraulik Reaktor Menggunakan RELAP5-3D], Tommy Suhartanto Wijaya Tan, 2018.
  33. Fuel Loading Pattern Optimization in KSNP-1000 to Extend Reactor Operating Time with Maximum Power Peaking Factor Constraint using Modified Bat Algorihm Method [Optimasi Susunan Bahan Bakar dalam Teras Reaktor KSNP-1000 untuk Memperpanjang Durasi Pengoperasian Reaktor dengan Batasan Faktor Pemuncakan Daya Maksimum Menggunakan Metode Algoritma Kelelawar Modifikasi], Yudi Riski Chandratama, 2018.
  34. Fuel Loading Pattern Optimization of KSNP-1000 with Minimum Power Peaking Factor and Reactor Operating Time using Modified Bat Algorithm Method [Optimasi Susunan Bahan Bakar Nuklir dalam Teras Reaktor KSNP-1000 dengan Faktor Pemuncakan Daya Minimal dan Rentang Waktu Operasi Reaktor Setara dengan Susunan Bahan Bakar Nuklir Standar Menggunakan Metode Modified Bat Algorithm], Kurniawan Adi Saputra, 2018.
  35. Planning Scenario of Electrical Energy Supply in Bangka Belitung Province with VBER-300 and KLT-40s Small Modular Reactors, Lazuwardi Imani, 2018.
  36. Thermal Hydraulics Analysis on the Core of High-Temperature Gas-Cooled Reactor (HTGR) 150 MWt in Steady State and Transient Condition with RELAP5-3D [Analisis Termal Hidraulika Teras High-Temperature Gas-Cooled Reactor (HTGR) 150 MWt pada Kondisi Steady State dan Transient menggunakan RELAP5-3D]. Matheus Ludfi, 2017.
  37. Designing Fuel Assembly in Small-PWR Using Uranium Mononitride Fully Ceramic Microencapsulated Based using SCALE and SERPENT [Perancangan Fuel Assembly Small-PWR Berbahan Bakar Uranium Mononitrida Berbasis Fully Ceramic Microencapsulated menggunakan SCALE dan SERPENT]. Arief Rahman Hakim, 2017.
  38. Thermal-hydraulic Analysis of the High-Temperature Gas-Cooled Reactor (HTGR) 150 MWt Steam Generator Parameter on Depressurized Loss of Forced Cooling (DLOFC) Accident Conditions using RELAP5-3D. [Analisis Termohidrolika Parameter Steam Generator dari High-Temperature Gas-cooled Reactor (HTGR) 150 MWt Pada Kondisi Depressurized Loss of Forced Cooling (DLOFC) Accident Menggunakan RELAP5-3D ]. Noval Wahyu Ardiansyah, 2017.
  39. Modeling and Analysis of Thermal Hydraulics Operation Parameters of KLT-40s Reactor at Steady and Transient Condition using RELAP5-3D [Pemodelan Dan Analisis Termal Hidraulika Parameter – Parameter Operasi Teras Reaktor KLT-40s Pada Kondisi Stabil (steady-state) dan Transien Menggunakan RELAP5-3D]. Abednego Kristanto, 2017.
  40. The Study of KLT-40s Floating Nuclear Power Plant Reactor Core Neutronic Parameter using SCALE 6.1 Simulation Code [Studi Parameter Neutronik Teras Reaktor PLTN Terapung KLT-40s Menggunakan Kode Simulasi SCALE 6.1 ]. Dhirar Faisal Fajri, 2017.
  41. Design Analysis of Fuel Assembly and Reactor Core of Floating Nuclear Power Plant KLT-40s using SERPENT Code. [Analisis Desain Fuel Assembly dan Teras Reaktor PLTN Terapung KLT-40s Menggunakan Kode Serpent]. Kevin Ahimsa, 2017.
  42. Neutronic Analysis of High-Temperature Reactor (HTR) with 7LiF-BeF2– Cooled Prismatic Type UO2-ThO2 [Analisis Neutronik High-Temperature Reactor (HTR) dengan Bahan Bakar UO2-ThO2 Tipe Prismatik Berpendingin 7LiF-BeF2]. Mardiono Abdi, 2017.
  43. Analisis Neutronik Teras One Fluid-Molten Salt Reactor (OF-MSR) Daya Rendah Berbasis Bahan Bakar LiF-235UF4–238UF4-ThF4 Menggunakan Kode Simulasi SCALE, Zakiyyuddin Rizky Rosanto, 2018.
  44. Neutronic Analysis of Aqueous Homogeneous Reactor (AHR) Breeder Design using Thorium Fuel at Critical Condition by Variating Mol Fraction Value [Analisis Neutronik Pada Desain Aqueous Homogeneous Reactor (AHR) Breeder Berbahan Bakar Thorium Pada Kondisi Kritis dengan Memvariasikan Nilai Fraksi Mol Bahan Bakar]. Azhim Kurniawan, 2017.
  45. Analysis on The Effect of Pitch Per Diameter Variation on Small-Sized Reduced-Moderation Water Reactor (S-RMWR) Fuel To The Neutronic Performance of Its Fuel Assembly Using SCALE 6.1 [Analisis Pengaruh Variasi Pitch Per Diameter Pada Bahan Bakar Small-sized Reduced-moderation Water Reactor (S-RMWR) Terhadap Performa Neutronik Fuel Assembly Reaktor Menggunakan SCALE 6.1.]. Frederik Darwin, 2017.
  46. Optimization of Beryllium Fraction in Blanket Design of Fusion Reactor to Achieve Tritium Breeding Using Monte Carlo Method. [Optimasi Fraksi Berilium Pada Desain Blanket Reaktor Fusi Untuk Mencapai Pembiakan Tritium Menggunakan Metode Monte Carlo]. Muhammad Ali, 2017.
  47. A Study on The Effects of Primary Thermohydraulic System Parameter Change on The Power and Void Fraction Generated in The Helical Coil Steam Generator for KLT-40s Reactor. [Studi Pengaruh Perubahan Parameter Termohidraulik Sistem Primer Terhadap Daya dan Fraksi Void yang Dihasilkan pada Helical Coil Steam Generator untuk Reaktor KLT-40s]. Sardini Sayyidatun Nisa, 2017.
  48. Thermal-hydraulic Analysis of Silicon Carbide and Zirconium Alloy as Cladding Material for Pressurized Water Reactor (PWR) During Large Break Loss Of Coolant Accident (LB-LOCA) In RELAP5-3D. [Analisis Termalhidraulik Silicon Carbide dan Zirconium Alloy sebagai Material Kelongsong Pressurized Water Reactor (PWR) Saat Kondisi Large Break Loss Of Coolant Accident (LB-LOCA) Menggunakan Software RELAP5-3D]. Julisa Bana Abraham, 2017.
  49. Core Design Parametric Study of True Travelling Wave Breed and Burn Reactor with Initial Active Core Low Enriched Uranium and Blanked Depleted Uranium using SRAC Code System.Wahid Luthfi, 2016
  50. Neutronic Analysis of Molten Salt Reactor Dual Fuel With Fuel 235U-238UF4-LiF and Modified Blanket 232ThF4–238UF4-LiF. Leo Wantda Oman, 2016.
  51. Simulation of Plasma Confinement in a Cylinder with Magnetic and Electric Field as Plasma Stabilizer for Fluid in a Fusion Reactor, Humam Fauzi, 2016.
  52. Analysis of Fuel Assembly Design in Small PWR using Uranium Nitride-based Fully Ceramic Microencapsulated Fuel on Soluble Boron Free Operational Conditions. Dedy Prasetyo Hermawan, 2016
  53. Neutronic Analysis of Reduced Moderation Boiling Water Reactor 1050 MWt. Dayu Fajrul Falah, 2016.
  54. Neutronic Analysis of HTR Experimental Power Reactor fueled with Thorium by Varying the core radius and fuel enrichment. Faisal Fuad Nursahid, 2016.
  55. Neutronic Analysis of HTR Experimental Power Reactor fueled with Uranium by Varying the core radius and fuel enrichment. Ganjar Putro Indratoro, 2016.
  56. Fuel Loading Pattern Optimization with Constraints on Fuel Assembly Inventories using Quantum-inspired Evolutionary Algorithm Method. M. Rizki Oktavian, 2016.
  57. Fuel Loading Pattern Optimization without Constraints on Fuel Assembly Inventories using Quantum-inspired Evolutionary Algorithm Method. Teguh Adi, 2016.
  58. Influence of Adding ZrC to the Buffer Zone of TRISO particle on the Multiplication Factor in a Fluidized Bed Nuclear Reactor. Mufid Panuntumi, 2016.
  59. Influence of Replacing SiC with ZrC in TRISO Particle Layer on the Multiplication Factor in a Fluidized Bed Nuclear Reactor. Christian Zulheri Siahaan, 2016.
  60. Determination of Absorbed Dose in Breast Cancer Brachytherapy using MCNP-X Code, Faisal Reza Rahmat, 2016.
  61. Neutronic Analysis of One-Fluid Molten Salt Reactor (OF-MSR) Core Based on LiF-U238F4-U235F4-ThF4 R. Andika Putra Dwijayanto, 2015.
  62. Core Design Optimization of Dual Fuel Molten Salt Reactor (MSR) using UF4–7LiF Core Fuel and 232ThF4–7LiF Blanket Fuel. M. Yayan Adi Putra, 2015.
  63. Optimization of Core Design of Molten Salt Reactor (MSR) Dual Fuel with Fuel UF4–7LiF and Blanket 238UF4–232ThF4–7LiF. Ilham Dwi Arirohman, 2015.
  64. Performance Simulation of Plasma Confinement in Cylinder with Magnetic and Electric Field as Base of Plasma Stability for Being Used as Fluid in Fusion Reactor. Humam Fauzi, 2015.
  65. Fusion Reactor Blanket Geometry Design Optimization for Tritium Breeding using Monte Carlo Method. Steven Wijaya, 2015
  66. Investigation of Xenon Oscillations at the Ringhals-3 PWR. Rikard Nylander, 2011 (Master program in Nuclear Engineering, Chalmers University of Technology).
  67. Flow Field Analysis of Fixed Bed Nuclear Reactor by means of CFD. Anif Hidayatullah, 2010.
  68. Preliminary Design of Long-lived Modular High-Temperature Reactor. Ayi Wirawan, 2010.
  69. Core and Fuel Design of 100 MWe Pebble Bed Modular Reactor using MCNP5. Winda Orcu, 2009.
  70. Core and Fuel Design of 50 MWe Pebble Bed Modular Reactor using MCNP5. Fitri, 2009.
  71. Implementation of Improved Genetic Algorithm Method to the Loading Pattern of PWR. Petrus, 2009.
  72. Implementation of Multi-objective Simulated Annealing Method for PWR Loading Pattern Optimization. Christina Novilla Soewono, 2009.
  73. Optimization of Burnable Poison Placement of PWR Core using Algorithm Genetics. Andin Nugroho, 2009.
  74. Optimization of Burnable Poison Placement of PWR Core using Multi-Objective Simulated Annealing. Damar Canggih Wicaksono, 2009.
  75. Influence of Electrical Current Density to the Performance of Electrolyzer in High-Temperature Electrolysis Process using Molten Salt Reactors. Arnoldus Lambertus Dipu, 2009.
  76. Audit Energi Listrik Studi Kasus di Gedung Puskesmas Piyungan Dinas Kesehatan Kabupaten Bantul Yogyakarta. Antun Hajar Hernawan, 2009.
  77. Optimization of Loading Pattern of PWR Core using Simulated Annealing Method. Luki Arif Mulyana, 2008.
  78. Optimization of Loading Pattern of PWR Core using Genetic Algorithm Methods. Yos Panagaman Sitompul, 2008.
  79. Preliminary Investigation of Neutronic Performance of Online Refueling of Passive Compact Molten Salt Reactor (PCMSR). Andi Permana Jati, 2008.
  80. Thermal-hydraulic Transient Analysis of Simple Small Safe Reactor (SSSR). Enjang Ruhiat, 2008
  81. Prediksi Loss Coefficient Pipa Berbelok 90º Menggunakan Fluent. Marthin Lokot Manurung, 2008.
  82. CFD Analysis of Fluid Flow in a Vortex Tube. Aris Ahmad Maniq, 2008.
  83. CFD Analysis of Fluid Flow at Tornado Type Wind Turbines (TTWT) using Fluent 6.2.16. Aditya Endrita Putra, 2008.
  84.  Simulation of Modified Savonius Turbine by Using CFD. Leksha Dusyanta Wirabhuana, 2008.
  85. Analysis of Control Rod Worth in a Fixed Bed Nuclear Reactor. Andin Nugroho, 2008, (student project).
  86. Determination of Optimum Pitch Cell Pin using Genetic Algorithm Methods and SRAC. Yos Panagaman Sitompul and Yuka Wilaga Yudha, 2007, (student project).
  87. The Influence of Variation of Molten Salt Reactor Output Temperature to the Efficiency of Hydrogen Production by Means of High-Temperature Electrolysis System. Elsa Melfiana, 2007.
  88. The Effect of Hydrogen Recycling in an Electrolyzer on The Performance of High-Temperature Electrolysis. Thomas Ari Negara, 2007.
  89.  Numerical Design of Oxygen Cooler in Electrolysis Process. Ferdinan Martin Sinaga, 2007.
  90. Detection of Explosive Materials using Gamma Rays By Means of Monte Carlo Simulation. Erwin Baharudin Ginting, 2007
  91.  Design of Condenser in a Mini Geothermal System with Silicate Extraction. Sunarti, 2007.
  92.  Energy Analysis on The Use of Peat As Fuel in a Power Plant. Fitriana, 2007.
  93.  Design of Axial Turbine for 2 MW Geothermal Power Generation. Raghunala Kusuma Marhaeni, 2007.
  94.  Exergy Analysis of Coal Boiler: A Case Study of PT APAC Inti Corpora. Sarah Nurina Amelia, 2007.
  95. Kajian Karakteristik Turbin Tesla dengan Variasi Dimensi Nozzle Secara Eksperimen. Hendri Rantau Silalahi, 2007.
  96. The Design of High-Temperature Molten Salt Fast Breeder Reactor. Fitri Wulandari, 2006.
  97. Neutronic and Safety Analysis of Fixed Bed Nuclear Reactor (FBNR) Using SRAC code. Wahyuni, 2006.
  98. The Effect of Cell Modeling in a Hypothetical PWR to the Infinite Multiplication Factor. Donny Hartanto, 2006, (student project).
  99. Feasibility Study of Fluidized Bed Nuclear Reactor (FLUBER) Fueled with ThO2-PuO2 as Pu-Burner. Suwondho Arie Prayudha, 2006.
  100. The Design of Pebble Bed AHFR (Advanced High-Temperature Fast Reactor) Fueled with Uranium-Thorium Carbides. Abdul Aziz Rahman Hakim, 2006.
  101. Neutronic Analysis of SCWR Fueled with Uranium-Thorium. Rony Prayitno Simeon, 2006.
  102. The Core Design of Supercritical Water-cooled Fast Breeder Reactor. Rohmad Sigit Eko Budi Prasetyo, 2006.
  103. Making of Graphical User Interface (GUI) for SRAC. Pambudi, 2006, (student project).
  104. Design of Collimator in Subcritical Beamport of Kartini Reactor for Neutron Radiography. Yohannes Puji Ari Purnomo, 2005.
  105. Design of Collimator in Radial Beamport of Kartini Reactor for Neutron Radiography. Denie Arifianto, 2005.
  106. Design of Collimator in Tangential Beamport of Kartini Reactor for Neutron Radiography. Dendi Ardiananto, 2005.
  107. Criticality and Fuel Consumption Analysis of 4 – 5% enriched KSNP-1000. Filian Arbiyani, 2005.
  108. Energy Analysis as a Mean to Increase Thermal Efficiency of Steam Power Generation (A Case Study of PT Indonesia Power PLTU Unit 3, Tambak Lorok, Semarang). Theresia Retno Nurmilasari,
  109. Study of the Influence of Bubble on Reactivity in FLUBER. Wiliam, 2003.