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Nitrate salt phase transition study for molten salt loop working fluid consideration

Heat and mass transfer, 2024, Vol.60 (1), p.117-132

2024

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The effect of Copper utilization on MSFR’s safety plug performance simulation by using MPS

Journal of physics. Conference series, 2022-06, Vol.2243 (1), p.12059

2022

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One Stage Method – Activated Carbon Modified by Surfactant and Irra-diation to Highly Improve Adsorption of Lead (II) Ion Wastewater Simulation (Utilization of Banana Peel Biomass)

Journal of Ecological Engineering, 2024-12, Vol.25 (12), p.70-82

2024

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Numerical Study on Relocation Process of Al, Fe, and Pb by Using the Moving Particle Semi-Implicit Method During Severe Accident of Reactor

International Journal of Technology, 2023-06, Vol.14 (4), p.800

2023

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Molten uranium eutectic interaction on iron-alloy by MPS method

Nuclear engineering and design, 2014-10, Vol.278, p.387-394

2014

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Comparison of Melted Corium Relocation during Severe Accident of High Temperature Reactor using Moving Particle Semi-Implicit Method

Computational and experimental research in materials and renewable energy, 2023-05, Vol.6 (1), p.1

2023

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High Temperature Oxidation Behavior of ODS Ferritic Stainless Steel Fe-16Cr-4Al-1Ni-0.4Y2O3

Indonesian journal of chemistry, 2024-10, Vol.24 (5), p.1456-1469

2024

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The Effect of Temperature Variations on Wood's Metal Plate Melting Simulation by Using MPS

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12024

2020

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3D simulation of eutectic interaction of Pb–Sn system using Moving Particle Semi-implicit (MPS) method

Annals of nuclear energy, 2015-07, Vol.81, p.26-33

2015

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Moving particle semi-implicit simulation on the molten Wood’s metal downward relocation process

Nuclear science and techniques, 2021-08, Vol.32 (8), p.110-121, Article 88

2021

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New Chemicals and Routes for the Preparation of Gelatin/HA Composites using the Wet Precipitation Method

Jurnal Kimia Sains dan Aplikasi, 2020-02, Vol.23 (2), p.46-50

2020

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Study on corrosion of welded steel for LBE-cooled fast reactors

Progress in nuclear energy (New series), 2011-09, Vol.53 (7), p.1073-1077

2011

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Simulation of melted UO2 on a 90° bend channel by using the moving particle semi-implicit method for reactor core catcher development

Nuclear engineering and design, 2024-10, Vol.427, p.113413, Article 113413

2024

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The molten salt phase transition study using computational fluid dynamics as a preliminary study of the molten salt loop experiment

AIP Conference Proceedings, 2024, Vol.3132 (1)

2024

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Comparison of the neutronic properties of the (Th- 233 U)O 2 , (Th- 233 U)C, and (Th- 233 U)N fuels in small long-life PWR cores with 300, 400, and 500 MW th of power

Nukleonika, 2024-03, Vol.69 (1), p.3-12

2024

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Irregular pentagon loop for nuclear reactor natural circulation system test apparatus

Nuclear engineering and design, 2024-01, Vol.416, p.112753, Article 112753

2024

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Neutronic design of small modular longlife pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth

Eastern-European journal of enterprise technologies, 2024-02, Vol.1 (8 (127)), p.18-27

2024

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Experimental study of solid low-density tilted plate’s erosion by low melting temperature molten materials

AIP Conference Proceedings, 2023, Vol.2623 (1)

2023

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Experimental and numerical analysis of impingement temperature effect on the sacrificial plate's hole formation during nuclear severe accident

Progress in nuclear energy (New series), 2023-08, Vol.162, p.104782, Article 104782

2023

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Analisis Image Processing pada Prasasti Teroksidasi Ayam Téas I

Purbawidya : jurnal penelitian dan pengembangan arkeologi = Journal of archeological research and development, 2023-11, Vol.12 (2), p.206-215

2023

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Simulation Of Mechanical Stress On A Solution-Annealed 15-15Ti Steel Using ABAQUS CAE Program

Jurnal Sains Materi Indonesia, 2024-08, Vol.26 (1), p.65-74

2024

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Study on Corrosion Properties of Welded Ferritic-Martensitic Steels in Liquid Lead-Bismuth at 600.DEG.C

Journal of power and energy systems, 2011, Vol.5 (1), p.69-76

2011

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INTERACTION OF MOLTEN URANIUM WITH ELECTRICAL PENETRATING TUBE OF A BOILING WATER REACTOR DURING SEVERE ACCIDENT

Jurnal iptek nuklir ganendra, 2020-09, Vol.23 (2), p.55

2020

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Metallurgical analysis of corroded bellows of bellow-sealed valve in lithium flow system

Fusion engineering and design, 2013-05, Vol.88 (4), p.202-208

2013

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Penerapan Metode Moving Particle Semi-Implicit dalam Simulasi Pelelehan Freeze Plug pada Molten Salt Reactor saat Terjadi Kecelakaan Reaktor

JST (Jurnal Sains dan Teknologi), 2024-01, Vol.12 (3)

2024

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Nitrate salt phase transition study for molten salt loop working fluid consideration

The effect of Copper utilization on MSFR’s safety plug performance simulation by using MPS

One Stage Method – Activated Carbon Modified by Surfactant and Irra-diation to Highly Improve Adsorption of Lead (II) Ion Wastewater Simulation (Utilization of Banana Peel Biomass)

Numerical Study on Relocation Process of Al, Fe, and Pb by Using the Moving Particle Semi-Implicit Method During Severe Accident of Reactor

Molten uranium eutectic interaction on iron-alloy by MPS method

Comparison of Melted Corium Relocation during Severe Accident of High Temperature Reactor using Moving Particle Semi-Implicit Method

High Temperature Oxidation Behavior of ODS Ferritic Stainless Steel Fe-16Cr-4Al-1Ni-0.4Y2O3

The Effect of Temperature Variations on Wood's Metal Plate Melting Simulation by Using MPS

3D simulation of eutectic interaction of Pb–Sn system using Moving Particle Semi-implicit (MPS) method

Moving particle semi-implicit simulation on the molten Wood’s metal downward relocation process

New Chemicals and Routes for the Preparation of Gelatin/HA Composites using the Wet Precipitation Method

Study on corrosion of welded steel for LBE-cooled fast reactors

Simulation of melted UO2 on a 90° bend channel by using the moving particle semi-implicit method for reactor core catcher development

The molten salt phase transition study using computational fluid dynamics as a preliminary study of the molten salt loop experiment

Comparison of the neutronic properties of the (Th- 233 U)O 2 , (Th- 233 U)C, and (Th- 233 U)N fuels in small long-life PWR cores with 300, 400, and 500 MW th of power

Irregular pentagon loop for nuclear reactor natural circulation system test apparatus

Neutronic design of small modular longlife pressurized water reactor using thorium carbide fuel at a power level of 300–500 MWth

Experimental study of solid low-density tilted plate’s erosion by low melting temperature molten materials

Experimental and numerical analysis of impingement temperature effect on the sacrificial plate's hole formation during nuclear severe accident

Analisis Image Processing pada Prasasti Teroksidasi Ayam Téas I

Simulation Of Mechanical Stress On A Solution-Annealed 15-15Ti Steel Using ABAQUS CAE Program

Study on Corrosion Properties of Welded Ferritic-Martensitic Steels in Liquid Lead-Bismuth at 600.DEG.C

INTERACTION OF MOLTEN URANIUM WITH ELECTRICAL PENETRATING TUBE OF A BOILING WATER REACTOR DURING SEVERE ACCIDENT

Metallurgical analysis of corroded bellows of bellow-sealed valve in lithium flow system

Penerapan Metode Moving Particle Semi-Implicit dalam Simulasi Pelelehan Freeze Plug pada Molten Salt Reactor saat Terjadi Kecelakaan Reaktor

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