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Evaluating the JEFF 3.1, ENDF/B-VII.0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel

Nuclear science and techniques, 2022-12, Vol.33 (12), p.173-189, Article 165

2022

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Multi-criteria decision making for nuclear power plant selection using fuzzy AHP: Evidence from Indonesia

Energy and AI, 2023-10, Vol.14, p.100263, Article 100263

2023

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Neutronic and Proliferation Resistance Analysis of Small Modular Pressurized Water Reactor with Various Fuel Types using SRAC 2006

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.12057

2024

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Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd 2 O 3 – UO 2 and Al 2 O 3 – B 4 C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.12061

2024

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Evaluated Material Attractiveness of Plutonium Composition from Economic Simplified Boiling Water Reactor (ESBWR)

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.12058

2024

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Probabilistic Dose Assessment from SB-LOCA Accident in Ujung Lemahabang Using TMI-2 Source Term

Science and Technology of Nuclear Installations, 2017-01, Vol.2017 (2017), p.1-8

2017

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Dynamic analysis of TMSR-500 reactor core

AIP Conference Proceedings, 2022, Vol.2501 (1)

2022

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Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd2O3 – UO2 and Al2O3 – B4C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.012061

2024

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Plutonium and Minor Actinides Utilization in FUJI-U1 Molten Salt Reactor

Journal of physics. Conference series, 2019-04, Vol.1204 (1), p.12132

2019

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Preliminary Design Study of Small Power 30-50 MWt Experiment Power Reactor based on High Temperature Pebble Bed Gas Cooled Reactor Technology

Journal of physics. Conference series, 2019-01, Vol.1127 (1), p.12024

2019

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Fuel Breeding Analysis On Low Moderated Fuel Ratio Based On Actinides Closed Water-Cooled Thorium Reactor

Journal of physics. Conference series, 2018-09, Vol.1090 (1), p.12061

2018

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Preliminary Study of 20 MWth Experiment Power Reactor based on Pebble Bed Reactor

Journal of physics. Conference series, 2017-07, Vol.877 (1), p.12058

2017

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Neutron flux distribution calculation for various spatial mesh of finite slab geometry using one-dimensional diffusion equation

AIP Conference Proceedings, 2019, Vol.2180 (1)

2019

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Comparative Evaluation on Several Reactor Type of Actinide Closed-Cycle Schemes

Journal of physics. Conference series, 2018-09, Vol.1090 (1), p.12011

2018

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Thermal–hydraulic analysis of wire-wrapped SFR test subassemblies by subchannel analysis method

Annals of nuclear energy, 2013-04, Vol.54, p.109-119

2013

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Computational fluid dynamics study on cross flow pressure drop for triangular array rod assemblies with wire

Annals of nuclear energy, 2016-01, Vol.87, p.803-816

2016

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Comparative Analysis on Fuel Breeding for Less Moderation Ratio of Water Cooled Reactor

Journal of physics. Conference series, 2019-04, Vol.1204 (1), p.12129

2019

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Preliminary Study of Plutonium Utilization in AP1000 Reactor

Journal of physics. Conference series, 2017-07, Vol.877 (1), p.12003

2017

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Comparative Studies on Plutonium and Minor Actinides Utilization in Small Molten Salt Reactors with Various Powers and Core Sizes

Energy procedia, 2015, Vol.71, p.62-68

2015

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Comparative studies on plutonium utilization in HTTR with helium and carbon dioxide gas coolants

International journal of hydrogen energy, 2016-05, Vol.41 (17), p.6984-6989

2016

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UO{sub 2} and PuO{sub 2} utilization in high temperature engineering test reactor with helium coolant

AIP conference proceedings, 2016-03, Vol.1719 (1)

2016

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Delayed Neutrons Effect on Power Reactor with Variation of Fluid Fuel Velocity at MSR Fuji-12

Journal of physics. Conference series, 2017-01, Vol.799 (1), p.12004

2017

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Preliminary Study on LiF4-ThF4-PuF4 Utilization as Fuel Salt of miniFUJI Molten Salt Reactor

Journal of physics. Conference series, 2016-08, Vol.739 (1), p.12004

2016

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Study on Utilization of Super Grade Plutonium in Molten Salt Reactor FUJI-U3 using CITATION Code

Journal of physics. Conference series, 2017-07, Vol.877 (1), p.12021

2017

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Core design study for power uprating of integral primary system PWR

Annals of nuclear energy, 2013-09, Vol.59, p.16-24

2013

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Evaluating the JEFF 3.1, ENDF/B-VII.0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel

Multi-criteria decision making for nuclear power plant selection using fuzzy AHP: Evidence from Indonesia

Neutronic and Proliferation Resistance Analysis of Small Modular Pressurized Water Reactor with Various Fuel Types using SRAC 2006

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd 2 O 3 – UO 2 and Al 2 O 3 – B 4 C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Evaluated Material Attractiveness of Plutonium Composition from Economic Simplified Boiling Water Reactor (ESBWR)

Probabilistic Dose Assessment from SB-LOCA Accident in Ujung Lemahabang Using TMI-2 Source Term

Dynamic analysis of TMSR-500 reactor core

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd2O3 – UO2 and Al2O3 – B4C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Plutonium and Minor Actinides Utilization in FUJI-U1 Molten Salt Reactor

Preliminary Design Study of Small Power 30-50 MWt Experiment Power Reactor based on High Temperature Pebble Bed Gas Cooled Reactor Technology

Fuel Breeding Analysis On Low Moderated Fuel Ratio Based On Actinides Closed Water-Cooled Thorium Reactor

Preliminary Study of 20 MWth Experiment Power Reactor based on Pebble Bed Reactor

Neutron flux distribution calculation for various spatial mesh of finite slab geometry using one-dimensional diffusion equation

Comparative Evaluation on Several Reactor Type of Actinide Closed-Cycle Schemes

Thermal–hydraulic analysis of wire-wrapped SFR test subassemblies by subchannel analysis method

Computational fluid dynamics study on cross flow pressure drop for triangular array rod assemblies with wire

Comparative Analysis on Fuel Breeding for Less Moderation Ratio of Water Cooled Reactor

Preliminary Study of Plutonium Utilization in AP1000 Reactor

Comparative Studies on Plutonium and Minor Actinides Utilization in Small Molten Salt Reactors with Various Powers and Core Sizes

Comparative studies on plutonium utilization in HTTR with helium and carbon dioxide gas coolants

UO{sub 2} and PuO{sub 2} utilization in high temperature engineering test reactor with helium coolant

Delayed Neutrons Effect on Power Reactor with Variation of Fluid Fuel Velocity at MSR Fuji-12

Preliminary Study on LiF4-ThF4-PuF4 Utilization as Fuel Salt of miniFUJI Molten Salt Reactor

Study on Utilization of Super Grade Plutonium in Molten Salt Reactor FUJI-U3 using CITATION Code

Core design study for power uprating of integral primary system PWR

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