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Molecular Dynamics Simulations of PtTi High-Temperature Shape Memory Alloys Based on a Modified Embedded-Atom Method Interatomic Potential

Materials, 2022-07, Vol.15 (15), p.5104

2022

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Influence of carbon content on static recrystallization behavior of 50% cold-rolled Fe-18Mn-9Cr-2Al-xC steels

Materials characterization, 2023-12, Vol.206, p.113365, Article 113365

Chun, Young-Bum

2023

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Low-Cycle Fatigue Behavior of Reduced Activation Ferritic-Martensitic Steel at Elevated Temperatures

Metals and materials international, 2023, Vol.29 (1), p.71-80

2023

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Effect of gadolinium addition on the corrosion behavior and oxide properties of titanium in boric acid solution at 50 °C

Journal of materials research and technology, 2022-11, Vol.21, p.3051-3061

2022

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Corrosion behavior of neutron absorbing Ti-Gd alloys in simulated spent nuclear fuel pool water

Corrosion science, 2022-12, Vol.209, p.110776, Article 110776

2022

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Prediction of the in-reactor deformation of Zr-2.5wt%Nb pressure tubes using the crystal plasticity finite element method framework

Journal of nuclear materials, 2022-11, Vol.570, p.153947, Article 153947

2022

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Microstructural Evolution of Oxide and Nitride Dispersed Nickel-Based Alloy Powders

Metals and Materials International, 2019, 25(1), , pp.140-146

2019

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Chemical compatibility between ARAA alloy and lithium meta-titanate breeder material

Fusion engineering and design, 2017-11, Vol.124, p.1052-1058

2017

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Ordered L10-FeNi (111) epitaxial thin film on Al2O3 (0001) substrate: Molecular beam epitaxy growth and characterizations

Thin solid films, 2023-09, Vol.780, p.139962, Article 139962

2023

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Atomistic investigation of phase transformations in NiTiCu shape memory alloys

International journal of mechanical sciences, 2024-07, Vol.274, Article 109256

2024

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Analysis of texture and grain shape effects on the yield anisotropy of Zr-2.5wt%Nb pressure tube alloy using crystal plasticity finite element method

Journal of nuclear materials, 2021-11, Vol.555, p.153112, Article 153112

2021

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Enhancement of strength and ductile-brittle transition temperature of SA508 Gr.3 low-alloy steel by controlling heat accumulation in laser powder-directed energy deposition

Journal of materials science & technology, 2024-12, Vol.202, p.240-252

2024

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Effects of B addition on microstructure and thermal conductivity of Cu-B composites produced by hot-extrusion of elemental powders

Powder metallurgy, 2023-10, Vol.ahead-of-print (ahead-of-print), p.1-7

2023

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Study on the mechanical properties and microstructure of Zr-2.5wt%Nb pressure tube material

Journal of nuclear materials, 2019-09, Vol.523, p.458-471

2019

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Uniformity of neutron absorber distribution in Gd-containing neutron absorber materials

Annals of nuclear energy, 2024-04, Vol.198, p.110288, Article 110288

2024

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Correction: Low-Cycle Fatigue Behavior of Reduced Activation Ferritic-Martensitic Steel at Elevated Temperatures

Metals and materials international, 2023, Vol.29 (7), p.2118-2118

2023

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Status of HCCR TBM program for DEMO blanket

Fusion engineering and design, 2021-10, Vol.171, p.112553, Article 112553

2021

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Microstructure evolution of a ZrC coating layer in TRISO particles during high-temperature annealing

Journal of nuclear materials, 2016-10, Vol.479, p.93-99

2016

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Investigation of technical gaps between DEMO blanket and HCCR TBM

Fusion engineering and design, 2018-11, Vol.136, p.190-198

2018

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원자력 사고 안전성 향상을 위한 SiC f /SiC 복합소재 개발 동향

Composites Research(구 한국복합재료학회지), 2022-06, Vol.35 (3), p.161-174

2022

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Design and R&D progress of Korean HCCR TBM

Fusion engineering and design, 2014-10, Vol.89 (7-8), p.1137-1143

2014

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Development of Advanced Structural Materials for Future Nuclear Systems in Korea

Procedia engineering, 2014, Vol.86, p.1-7

2014

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Low-Cycle Fatigue Behavior of Reduced Activation Ferritic-Martensitic Steel at Elevated Temperatures

Metals and materials international, 2023-01, p.71-80

2023

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Evaluation of Hot Deformation and Dynamic Recrystallization Behaviors of Advanced Reduced-Activated Alloy (ARAA)

Metals and materials international, 2019-07, p.888-899

2019

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Radiation damage of F/M and ODS alloys after Fe3+-ion irradiation at 300 °C

Journal of the Korean Physical Society, 2015, 66(3), , pp.505-508

2015

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Molecular Dynamics Simulations of PtTi High-Temperature Shape Memory Alloys Based on a Modified Embedded-Atom Method Interatomic Potential

Influence of carbon content on static recrystallization behavior of 50% cold-rolled Fe-18Mn-9Cr-2Al-xC steels

Low-Cycle Fatigue Behavior of Reduced Activation Ferritic-Martensitic Steel at Elevated Temperatures

Effect of gadolinium addition on the corrosion behavior and oxide properties of titanium in boric acid solution at 50 °C

Corrosion behavior of neutron absorbing Ti-Gd alloys in simulated spent nuclear fuel pool water

Prediction of the in-reactor deformation of Zr-2.5wt%Nb pressure tubes using the crystal plasticity finite element method framework

Microstructural Evolution of Oxide and Nitride Dispersed Nickel-Based Alloy Powders

Chemical compatibility between ARAA alloy and lithium meta-titanate breeder material

Ordered L10-FeNi (111) epitaxial thin film on Al2O3 (0001) substrate: Molecular beam epitaxy growth and characterizations

Atomistic investigation of phase transformations in NiTiCu shape memory alloys

Analysis of texture and grain shape effects on the yield anisotropy of Zr-2.5wt%Nb pressure tube alloy using crystal plasticity finite element method

Enhancement of strength and ductile-brittle transition temperature of SA508 Gr.3 low-alloy steel by controlling heat accumulation in laser powder-directed energy deposition

Effects of B addition on microstructure and thermal conductivity of Cu-B composites produced by hot-extrusion of elemental powders

Study on the mechanical properties and microstructure of Zr-2.5wt%Nb pressure tube material

Uniformity of neutron absorber distribution in Gd-containing neutron absorber materials

Correction: Low-Cycle Fatigue Behavior of Reduced Activation Ferritic-Martensitic Steel at Elevated Temperatures

Status of HCCR TBM program for DEMO blanket

Microstructure evolution of a ZrC coating layer in TRISO particles during high-temperature annealing

Investigation of technical gaps between DEMO blanket and HCCR TBM

원자력 사고 안전성 향상을 위한 SiC f /SiC 복합소재 개발 동향

Design and R&D progress of Korean HCCR TBM

Development of Advanced Structural Materials for Future Nuclear Systems in Korea

Low-Cycle Fatigue Behavior of Reduced Activation Ferritic-Martensitic Steel at Elevated Temperatures

Evaluation of Hot Deformation and Dynamic Recrystallization Behaviors of Advanced Reduced-Activated Alloy (ARAA)

Radiation damage of F/M and ODS alloys after Fe3+-ion irradiation at 300 °C

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