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The Effect of Adding Minor Actinide Fuel Rods on GFR Reactor in Radiopharmaceutical Waste Production Using OpenMC Program

Science & technology Indonesia, 2024-10, Vol.9 (4), p.857-865

2024

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Validation of OpenMC Code for Low-cycle and Low-particle Simulations in the Neutronic Calculation

JIF (Jurnal Ilmu Fisika), 2024-05, Vol.16 (2), p.107-117

2024

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Filtration efficiency analysis of cotton cloth-based mask for reducing transmission rate of COVID-19 using PM2.5 detection methods

Journal of physics. Conference series, 2022-06, Vol.2243 (1), p.12067

2022

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Thermalhydraulic calculation for boiling water reactor and its natural circulation component

AIP Conference Proceedings, 2015, Vol.1677 (1)

2015

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Preliminary design study of small long life boiling water reactor (BWR) with tight lattice thorium nitride fuel

AIP Conference Proceedings, 2014, Vol.1615 (1), p.84

2014

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Nuclear Energy Contribution for Net Zero Emission and National Energy Mix 2060 in Indonesia

Journal of physics. Conference series, 2022-06, Vol.2243 (1), p.12066

2022

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3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code

Nuclear engineering and design, 2024-08, Vol.425, p.113340, Article 113340

2024

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Neutronic performance evaluation of Plutonium Recycling in two core sizes for a 250 MWt Molten salt reactor

Nuclear engineering and design, 2023-12, Vol.415, p.112733, Article 112733

2023

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Neutronic design performance of 100 MWe MSR with thorium-enriched uranium and thorium-plutonium-minor actinide fuel

Nuclear engineering and design, 2023-12, Vol.414, p.112646, Article 112646

2023

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Neutronic performance of (Th-233U) nitride and oxide for hexagonal tight lattice fuel cell of boiling water reactor

AIP Conference Proceedings, 2023, Vol.2893 (1)

2023

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Optimum power determination and comparison of multi-pass and OTTO fuel management schemes of HTGR-based PeLUIt reactor

Nuclear engineering and design, 2023-12, Vol.415, p.112696, Article 112696

2023

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Neutronic and thermal-hydraulic analysis for TRIGA Mark II in subcooled nucleate boiling condition

Nuclear engineering and design, 2024-05, Vol.421, p.113092, Article 113092

2024

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Subcooled boiling prediction on current fuel configuration of TRIGA 2000 reactor core by COOLOD-N2 code

AIP Conference Proceedings, 2024, Vol.2967 (1)

2024

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Nuclear energy contribution potential to secure electricity demand with low carbon emission and low risk of power plant in Indonesia

IOP conference series. Earth and environmental science, 2021-05, Vol.753 (1), p.12048

2021

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Identification of thermal neutron flux in central thimble of TRIGA 2000 reactor with experimental method

AIP Conference Proceedings, 2023, Vol.2893 (1)

2023

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Enhancing the neutronic performance of SMART Small modular reactor using alternative fuel material

Annals of nuclear energy, 2025-02, Vol.211, p.110895, Article 110895

2025

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Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme

Nuclear engineering and design, 2024-06, Vol.422, p.113163, Article 113163

2024

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Validation of OpenMC Code Criticality Value Calculation for GFR Reactor with UN-PuN Fuel

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.12065

2024

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ANALYSIS OF CORE CONFIGURATION FOR CONCEPTUAL GAS COOLED FAST REACTOR (GFR) USING OPENMC

Jurnal teknologi reaktor nukir Tri Dasa Mega, 2023-07, Vol.25 (2), p.85

2023

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Comparison of thermal-hydraulic calculation in 100 MWt thorium-based HTGR using SiC and ZrC TRISO coated fuel particle

Nuclear engineering and design, 2023-10, Vol.412, p.112463, Article 112463

2023

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A comparative analysis of gas-cooled fast reactor using heterogeneous core configurations with three and five fuel variations

Eastern-European journal of enterprise technologies, 2024-02, Vol.1 (8 (127)), p.6-17

2024

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Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer

Kerntechnik (1987), 2023-08, Vol.88 (4), p.503-517

2023

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Preliminary Analysis of Unprotected Loss of Heat Sink in Small Long Life Gas Cooled Fast Reactor

Applied Mechanics and Materials, 2015-04, Vol.751 (Materials Science, Applied Mechanics and Advanced Engineering Research), p.268-272

2015

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Power Flattening on Design Study of Small Long-Life Boiling Water Reactor (BWR) with Tight Lattice Thorium Nitride Fuel

Applied Mechanics and Materials, 2015-04, Vol.751 (Materials Science, Applied Mechanics and Advanced Engineering Research), p.257-262

2015

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Neutronic Performance of Small Long-Life Boiling Water Reactor Using Thorium as Fuel and the Addition of Protactinium as Burnable Poisons

Advanced materials research, 2013-09, Vol.772, p.495-500

2013

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The Effect of Adding Minor Actinide Fuel Rods on GFR Reactor in Radiopharmaceutical Waste Production Using OpenMC Program

Validation of OpenMC Code for Low-cycle and Low-particle Simulations in the Neutronic Calculation

Filtration efficiency analysis of cotton cloth-based mask for reducing transmission rate of COVID-19 using PM2.5 detection methods

Thermalhydraulic calculation for boiling water reactor and its natural circulation component

Preliminary design study of small long life boiling water reactor (BWR) with tight lattice thorium nitride fuel

Nuclear Energy Contribution for Net Zero Emission and National Energy Mix 2060 in Indonesia

3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code

Neutronic performance evaluation of Plutonium Recycling in two core sizes for a 250 MWt Molten salt reactor

Neutronic design performance of 100 MWe MSR with thorium-enriched uranium and thorium-plutonium-minor actinide fuel

Neutronic performance of (Th-233U) nitride and oxide for hexagonal tight lattice fuel cell of boiling water reactor

Optimum power determination and comparison of multi-pass and OTTO fuel management schemes of HTGR-based PeLUIt reactor

Neutronic and thermal-hydraulic analysis for TRIGA Mark II in subcooled nucleate boiling condition

Subcooled boiling prediction on current fuel configuration of TRIGA 2000 reactor core by COOLOD-N2 code

Nuclear energy contribution potential to secure electricity demand with low carbon emission and low risk of power plant in Indonesia

Identification of thermal neutron flux in central thimble of TRIGA 2000 reactor with experimental method

Enhancing the neutronic performance of SMART Small modular reactor using alternative fuel material

Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme

Validation of OpenMC Code Criticality Value Calculation for GFR Reactor with UN-PuN Fuel

ANALYSIS OF CORE CONFIGURATION FOR CONCEPTUAL GAS COOLED FAST REACTOR (GFR) USING OPENMC

Comparison of thermal-hydraulic calculation in 100 MWt thorium-based HTGR using SiC and ZrC TRISO coated fuel particle

A comparative analysis of gas-cooled fast reactor using heterogeneous core configurations with three and five fuel variations

Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer

Preliminary Analysis of Unprotected Loss of Heat Sink in Small Long Life Gas Cooled Fast Reactor

Power Flattening on Design Study of Small Long-Life Boiling Water Reactor (BWR) with Tight Lattice Thorium Nitride Fuel

Neutronic Performance of Small Long-Life Boiling Water Reactor Using Thorium as Fuel and the Addition of Protactinium as Burnable Poisons

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