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Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating

Journal of nuclear materials, 2015-10, Vol.465, p.531-539

2015

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Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea

Nuclear Engineering and Technology, 2016, 48(1), , pp.1-15

2016

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Radioactivity release from the Fukushima accident and its consequences: A review

Progress in nuclear energy (New series), 2014-07, Vol.74, p.61-70

2014

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The ATSC Link-layer Protocol (ALP): Design and Efficiency Evaluation

IEEE transactions on broadcasting, 2016-03, Vol.62 (1), p.316-327

2016

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Development status of microcell UO2 pellet for accident-tolerant fuel

Nuclear engineering and technology, 2018-03, Vol.50 (2), p.253-258

2018

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High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings

Surface & coatings technology, 2015-10, Vol.280, p.256-259

2015

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A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment

Corrosion science, 2015-05, Vol.94, p.459-465

2015

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Thermodynamic Evaluation of Equilibrium Oxygen Composition of UO2-Mo Nuclear Fuel Pellet Under High Temperature Steam

Frontiers in energy research, 2021-07, Vol.9

2021

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Effect of a surface oxide-dispersion-strengthened layer on mechanical strength of zircaloy-4 tubes

Nuclear engineering and technology, 2018-03, Vol.50 (2), p.218-222

2018

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Optimization of degree-profile matching interleavers for LDPC-coded modulation

IEEE communications letters, 2006-12, Vol.10 (12), p.843-845

2006

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MICROSTRUCTURE AND MECHANICAL STRENGTH OF SURFACE ODS TREATED ZIRCALOY-4 SHEET USING LASER BEAM SCANNING

Nuclear Engineering and Technology, 2014, 46(4), , pp.521-528

2014

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Mixed analytical model to estimate the anisotropic effective thermal conductivity and in-reactor performance of metallic microcell UO2

Journal of nuclear materials, 2023-11, Vol.585, p.154655, Article 154655

2023

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UO2–UN composites with enhanced uranium density and thermal conductivity

Journal of nuclear materials, 2015-10, Vol.465, p.509-515

2015

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Numerical investigation of the thermal conductivity of UO2 – Mo microplate fuel pellets to realize enhanced heat transfer in the fuel radial direction

Journal of nuclear materials, 2021-10, Vol.554, p.153075, Article 153075

2021

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Analysis of pellet-to-cladding gap closure for a metallic micro-cell pellet under normal operating conditions

Journal of nuclear materials, 2021-12, Vol.556, p.153186, Article 153186

2021

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Gallager's Decoding Algorithm A over High Order Modulations

IEEE communications letters, 2009-05, Vol.13 (5), p.336-338

2009

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Oxidation and phase separation of U3Si2 nuclear fuel in high-temperature steam environments

Journal of nuclear materials, 2020-12, Vol.542, p.152517, Article 152517

2020

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Fabrication of micro-cell UO2–Mo pellet with enhanced thermal conductivity

Journal of nuclear materials, 2015-07, Vol.462, p.289-295

2015

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Oxidation behavior of silicon carbide at 1200°C in both air and water–vapor-rich environments

Corrosion science, 2014-11, Vol.88, p.416-422

2014

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Fission gas release in the micro-cell fuel pellet under normal operating conditions: A simplified approach based on UO2 pellet experience

Journal of nuclear materials, 2019-12, Vol.527, p.151801, Article 151801

2019

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IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR

Nuclear Engineering and Technology, 2014, 46(3), , pp.423-430

2014

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RECYCLING PROCESS OF U3O8 POWDER IN MnO-Al2O3 DOPED LARGE GRAIN UO2 PELLETS

Nuclear Engineering and Technology, 2014, 46(1), , pp.117-124

2014

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Effect of TiSi2/Ti3SiC2 matrix phases in a reaction-bonded SiC on mechanical and high-temperature oxidation properties

Journal of the European Ceramic Society, 2016-05, Vol.36 (6), p.1343-1348

2016

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INFLUENCE OF ALLOY COMPOSITION ON WORK HARDENING BEHAVIOR OF ZIRCONIUM-BASED ALLOYS

Nuclear Engineering and Technology, 2013, 45(4), , pp.505-512

2013

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KAERI's Development of LWR Accident-Tolerant Fuel

Nuclear technology, 2014-05, Vol.186 (2), p.295-304

2014

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Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating

Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea

Radioactivity release from the Fukushima accident and its consequences: A review

The ATSC Link-layer Protocol (ALP): Design and Efficiency Evaluation

Development status of microcell UO2 pellet for accident-tolerant fuel

High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings

A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment

Thermodynamic Evaluation of Equilibrium Oxygen Composition of UO2-Mo Nuclear Fuel Pellet Under High Temperature Steam

Effect of a surface oxide-dispersion-strengthened layer on mechanical strength of zircaloy-4 tubes

Optimization of degree-profile matching interleavers for LDPC-coded modulation

MICROSTRUCTURE AND MECHANICAL STRENGTH OF SURFACE ODS TREATED ZIRCALOY-4 SHEET USING LASER BEAM SCANNING

Mixed analytical model to estimate the anisotropic effective thermal conductivity and in-reactor performance of metallic microcell UO2

UO2–UN composites with enhanced uranium density and thermal conductivity

Numerical investigation of the thermal conductivity of UO2 – Mo microplate fuel pellets to realize enhanced heat transfer in the fuel radial direction

Analysis of pellet-to-cladding gap closure for a metallic micro-cell pellet under normal operating conditions

Gallager's Decoding Algorithm A over High Order Modulations

Oxidation and phase separation of U3Si2 nuclear fuel in high-temperature steam environments

Fabrication of micro-cell UO2–Mo pellet with enhanced thermal conductivity

Oxidation behavior of silicon carbide at 1200°C in both air and water–vapor-rich environments

Fission gas release in the micro-cell fuel pellet under normal operating conditions: A simplified approach based on UO2 pellet experience

IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR

RECYCLING PROCESS OF U3O8 POWDER IN MnO-Al2O3 DOPED LARGE GRAIN UO2 PELLETS

Effect of TiSi2/Ti3SiC2 matrix phases in a reaction-bonded SiC on mechanical and high-temperature oxidation properties

INFLUENCE OF ALLOY COMPOSITION ON WORK HARDENING BEHAVIOR OF ZIRCONIUM-BASED ALLOYS

KAERI's Development of LWR Accident-Tolerant Fuel

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