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Antioxidant Activity Between Defatted and Different Solvent Temperature in Rice Bran var. IR-64 Extract

E3S Web of Conferences, 2023, Vol.374, p.28

2023

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Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Science and Technology of Nuclear Installations, 2022-12, Vol.2022, p.1-12

2022

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Wall Effect Analysis in Thermal-Hydraulics Aspect of HTR-10 and PR-3000 Reactors Using Different Porosity Models

Science & technology Indonesia, 2021-10, Vol.6 (4)

2021

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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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Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant

Nuclear engineering and technology, 2021-02, Vol.53 (2), p.423-429

2021

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Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.12055

2024

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Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme

Annals of nuclear energy, 2013-10, Vol.60, p.383-395

2013

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A benchmark study of large-angle neutron scattering cross section of tungsten using two shadow bars technique at 14 MeV

EPJ Web of Conferences, 2023, Vol.284, p.7002

2023

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Burnup characteristics and fuel cycle economics of mixed uranium-thorium fuel in a simplified small pebble bed reactor

Journal of nuclear science and technology, 2012-02, Vol.49 (2), p.222-229

2012

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Preliminary Neutronic Analysis of 150 MWt High-Temperature Gas Reactor to Produced Electricity in Small Area

Journal of physics. Conference series, 2021-11, Vol.2072 (1), p.12011

2021

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Properties of Oil Palm Empty Fruit Bunch-Filled Recycled Acrylonitrile Butadiene Styrene Composites: Effect of Shapes and Filler Loadings with Random Orientation

Bioresources, 2017-01, Vol.12 (1), p.1090-1101

2017

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Burnup Characteristics of a Peu à Peu Fuel Loading Scheme in a 110MWt Simplified Pebble Bed Reactor

Journal of nuclear science and technology, 2011-11, Vol.48 (11), p.1385-1395

2011

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Biocomposites Formulated with Virgin/Recycled Acrylonitrile Butadiene Styrene

Materials science forum, 2017-07, Vol.900, p.23-26

2017

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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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Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycle

Nuclear engineering and design, 2024-03, Vol.418, p.112934, Article 112934

2024

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Study on the Effects of Enrichment and Fraction of Coated Fuel Particles on Fissile Utilization of 100 MWt Prismatic-type of High Temperature Gas Reactor

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12027

2020

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Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power

International journal of energy research, 2022-03, Vol.46 (4), p.4852-4868

2022

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Core design selection for a long‐life modular gas‐cooled fast reactor using OpenMC code

International journal of energy research, 2022-06, Vol.46 (7), p.9389-9403

2022

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Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling

MATEC Web of Conferences, 2016, Vol.82, p.3008

2016

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OpenMOC simulation for core-133 and core-134 of the TRIGA Mark II Research Reactor

AIP Conference Proceedings, 2022, Vol.2525 (1)

2022

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Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code

International journal of energy research, 2021-06, Vol.45 (8), p.12071-12085

2021

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Connected Floating Balls Dynamics for Harvesting Energy of Sinusoidal Water Wave

Journal of physics. Conference series, 2021-02, Vol.1772 (1), p.12011

2021

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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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Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy

Science and Technology of Nuclear Installations, 2022-12, Vol.2022

2022

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Antioxidant Activity Between Defatted and Different Solvent Temperature in Rice Bran var. IR-64 Extract

Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Wall Effect Analysis in Thermal-Hydraulics Aspect of HTR-10 and PR-3000 Reactors Using Different Porosity Models

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

Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant

Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor

Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme

A benchmark study of large-angle neutron scattering cross section of tungsten using two shadow bars technique at 14 MeV

Burnup characteristics and fuel cycle economics of mixed uranium-thorium fuel in a simplified small pebble bed reactor

Preliminary Neutronic Analysis of 150 MWt High-Temperature Gas Reactor to Produced Electricity in Small Area

Properties of Oil Palm Empty Fruit Bunch-Filled Recycled Acrylonitrile Butadiene Styrene Composites: Effect of Shapes and Filler Loadings with Random Orientation

Burnup Characteristics of a Peu à Peu Fuel Loading Scheme in a 110MWt Simplified Pebble Bed Reactor

Biocomposites Formulated with Virgin/Recycled Acrylonitrile Butadiene Styrene

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

Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycle

Study on the Effects of Enrichment and Fraction of Coated Fuel Particles on Fissile Utilization of 100 MWt Prismatic-type of High Temperature Gas Reactor

Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power

Core design selection for a long‐life modular gas‐cooled fast reactor using OpenMC code

Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling

OpenMOC simulation for core-133 and core-134 of the TRIGA Mark II Research Reactor

Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code

Connected Floating Balls Dynamics for Harvesting Energy of Sinusoidal Water Wave

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

Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy

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