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Development of a critical heat flux mapping method for fin-structured surfaces

Journal of nuclear science and technology, 2016-09, Vol.53 (9), p.1321-1331

2016

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The Direct Contact Condensation of Steam in a Pool at Low Mass Flux

Journal of Nuclear Science and Technology, 2003-10, Vol.40 (10), p.881-885

2003

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Wastage and Self-Plugging by a Potential CO2 Ingress in a Supercritical CO2 Power Conversion System of an SFR

Journal of nuclear science and technology, 2010-11, Vol.47 (11), p.1023

2010

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Assessment of the two-phase flow models in the CUPID code using the downcomer boiling experiment

Journal of nuclear science and technology, 2012-01, Vol.49 (1), p.78-89

2012

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Wastage and Self-Plugging by a Potential CO2 Ingress in a Supercritical CO2 Power Conversion System of an SFR

Journal of nuclear science and technology, 2010-11, Vol.47 (11), p.1023-1036

2010

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Wastage and Self-Plugging by a Potential CO 2 Ingress in a Supercritical CO 2 Power Conversion System of an SFR

Journal of nuclear science and technology, 2010-11, Vol.47 (11), p.1023-1036

2010

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The Direct Contact Condensation of Steam in a Pool at Low Mass Flux

Journal of nuclear science and technology, 2003-10, Vol.40 (10), p.881

2003

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A Feasibility study on a Dual-beam Port Assembly for Accelerator-Based Boron Neutron Capture Therapy

Journal of nuclear science and technology, 2008-06, Vol.45 (sup5), p.197-200

2008

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Fabrication of Sintered Annular Fuel Pellet for HANARO Irradiation Test

Journal of nuclear science and technology, 2010-04, Vol.47 (4), p.345-350

2010

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Improvement of UO2 Pellet Properties by Controlling the Powder Morphology of Recycled U3O8 Powder

Journal of nuclear science and technology, 2008-11, Vol.45 (11), p.1150-1154

2008

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Wastage and Self-Plugging by a Potential CO sub(2) Ingress in a Supercritical CO sub(2) Power Conversion System of an SFR

Journal of nuclear science and technology, 2010-01, Vol.47 (11)

2010

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Effects of MnO-Al2O3 on the Grain Growth and High-Temperature Deformation Strain of UO2 Fuel Pellets

Journal of nuclear science and technology, 2010-03, Vol.47 (3), p.304-307

2010

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Performance Evaluation of a Beam-shaping Assembly for Accelerated-BNCT Using the Neutron Generation Experiment of7 Li(p,n)7 Be Reaction

Journal of nuclear science and technology, 2008-06, Vol.45 (sup5), p.143-146

2008

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Performance Evaluation of a Beam-shaping Assembly for Accelerated-BNCT Using the Neutron Generation Experiment of 7 Li(p,n) 7 Be Reaction

Journal of nuclear science and technology, 2008-06, Vol.45 (sup5), p.143-146

2008

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Off-take and Slug Transition at T-junction of Vertical-up Branch in the Horizontal Pipe

Journal of nuclear science and technology, 2003-05, Vol.40 (5), p.317-324

2003

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Off-take and Slug Transition at T-junction of Vertical-up Branch in the Horizontal Pipe

Journal of nuclear science and technology, 2003-05, Vol.40 (5), p.317

2003

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High-Resolution Neutron-Induced ϒ-Ray Production Cross Sections for Oxygen and Beryllium for Neutron Energies from 4 to 200 MeV

Journal of nuclear science and technology, 2002-08, Vol.39 (sup2), p.401-404

2002

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Electrolytic Removal of Ag(I) in the Liquid Wastes Generated from the Mediated Electrochemical Oxidation Process

Journal of nuclear science and technology, 2000-02, Vol.37 (2), p.173-179

2000

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A Normalization Method for Relationship between Yield Stress and Delayed Hydride Cracking Velocity in Zr-2.5Nb Alloys

Journal of nuclear science and technology, 2000-07, Vol.37 (7), p.595-600

2000

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Evaluation of photonuclear reaction data on tantalum-181 up to 140 MeV

Journal of nuclear science and technology, 1998-10, Vol.35 (10), p.685-691

1998

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A Normalization Method for Relationship between Yield Stress and Delayed Hydride Cracking Velocity in Zr-2.5Nb Alloys

Journal of nuclear science and technology, 2000-07, Vol.37 (7), p.595

2000

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Evaluation of Neutron- and Proton-induced Nuclear Data on 27Al up to 2 GeV

Journal of nuclear science and technology, 1999-12, Vol.36 (12), p.1125-1134

1999

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Absolute Partial γ-ray Cross Sections in 238 U( n, xny ) Reactions

Journal of nuclear science and technology, 2002-08, Vol.39 (sup2), p.234-237

2002

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Absolute Partial γ-ray Cross Sections in 238U(n, xny) Reactions

Journal of nuclear science and technology, 2002-08, Vol.39, p.234-237

2002

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Vibration Monitoring of Core Support Barrel by Noise and Structural Analysis in ULJIN Nuclear Plant

Journal of nuclear science and technology, 1990-11, Vol.27 (11), p.1058-1064

1990

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Development of a critical heat flux mapping method for fin-structured surfaces

The Direct Contact Condensation of Steam in a Pool at Low Mass Flux

Wastage and Self-Plugging by a Potential CO2 Ingress in a Supercritical CO2 Power Conversion System of an SFR

Assessment of the two-phase flow models in the CUPID code using the downcomer boiling experiment

Wastage and Self-Plugging by a Potential CO2 Ingress in a Supercritical CO2 Power Conversion System of an SFR

Wastage and Self-Plugging by a Potential CO 2 Ingress in a Supercritical CO 2 Power Conversion System of an SFR

The Direct Contact Condensation of Steam in a Pool at Low Mass Flux

A Feasibility study on a Dual-beam Port Assembly for Accelerator-Based Boron Neutron Capture Therapy

Fabrication of Sintered Annular Fuel Pellet for HANARO Irradiation Test

Improvement of UO2 Pellet Properties by Controlling the Powder Morphology of Recycled U3O8 Powder

Wastage and Self-Plugging by a Potential CO sub(2) Ingress in a Supercritical CO sub(2) Power Conversion System of an SFR

Effects of MnO-Al2O3 on the Grain Growth and High-Temperature Deformation Strain of UO2 Fuel Pellets

Performance Evaluation of a Beam-shaping Assembly for Accelerated-BNCT Using the Neutron Generation Experiment of7 Li(p,n)7 Be Reaction

Performance Evaluation of a Beam-shaping Assembly for Accelerated-BNCT Using the Neutron Generation Experiment of 7 Li(p,n) 7 Be Reaction

Off-take and Slug Transition at T-junction of Vertical-up Branch in the Horizontal Pipe

Off-take and Slug Transition at T-junction of Vertical-up Branch in the Horizontal Pipe

High-Resolution Neutron-Induced ϒ-Ray Production Cross Sections for Oxygen and Beryllium for Neutron Energies from 4 to 200 MeV

Electrolytic Removal of Ag(I) in the Liquid Wastes Generated from the Mediated Electrochemical Oxidation Process

A Normalization Method for Relationship between Yield Stress and Delayed Hydride Cracking Velocity in Zr-2.5Nb Alloys

Evaluation of photonuclear reaction data on tantalum-181 up to 140 MeV

A Normalization Method for Relationship between Yield Stress and Delayed Hydride Cracking Velocity in Zr-2.5Nb Alloys

Evaluation of Neutron- and Proton-induced Nuclear Data on 27Al up to 2 GeV

Absolute Partial γ-ray Cross Sections in 238 U( n, xny ) Reactions

Absolute Partial γ-ray Cross Sections in 238U(n, xny) Reactions

Vibration Monitoring of Core Support Barrel by Noise and Structural Analysis in ULJIN Nuclear Plant

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