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Forced and mixed convection heat transfer to supercritical CO2 vertically flowing in a uniformly-heated circular tube

Experimental thermal and fluid science, 2010-11, Vol.34 (8), p.1295-1308

2010

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Convective heat transfer to CO2 at a supercritical pressure flowing vertically upward in tubes and an annular channel

Experimental thermal and fluid science, 2009, Vol.33 (2), p.329-339

2009

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Effect of a helical wire on mixed convection heat transfer to carbon dioxide in a vertical circular tube at supercritical pressures

The International journal of heat and fluid flow, 2011-02, Vol.32 (1), p.340-351

2011

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Enhancement of Pool Boiling Heat Transfer in Water Using Sintered Copper Microporous Coatings

Nuclear Engineering and Technology, 2016, 48(4), , pp.932-940

2016

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Experimental study on single- and two-phase flow behaviors within porous particle beds

Nuclear Engineering and Technology, 2023, 55(3), , pp.1105-1117

2023

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NUMERICAL INVESTIGATION OF THE SPREADING AND HEAT TRANSFER CHARACTERISTICS OF EX-VESSEL CORE MELT

Nuclear Engineering and Technology, 2013, 45(1), , pp.21-28

2013

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Development of safety injection flow map associated with target depressurization for effective severe accident management of OPR1000

Journal of nuclear science and technology, 2016-10, Vol.53 (10), p.1502-1512

2016

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Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART

Nuclear engineering and technology, 2022-12, Vol.54 (12), p.4551-4559

2022

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Effectiveness and adverse effects of in-vessel retention strategies under a postulated SGTR accident of an OPR1000

Journal of nuclear science and technology, 2017-03, Vol.54 (3), p.337-347

2017

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Introduction of filtered containment venting system experimental facility in KAERI and results of aerosol test

Nuclear engineering and design, 2018-01, Vol.326, p.344-353

2018

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Effectiveness and adverse effects of reactor coolant system depressurization strategy with various severe accident management guidance entry conditions for OPR1000

Journal of nuclear science and technology, 2015-05, Vol.52 (5), p.695-708

2015

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Pool boiling heat transfer of a copper microporous coating in borated water

Nuclear Engineering and Technology, 2020, 52(9), , pp.1939-1944

2020

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Validation of RCS depressurization strategy and core coolability map for independent scenarios of SBLOCA, SBO, and TLOFW

Journal of nuclear science and technology, 2014-02, Vol.51 (2), p.181-195

2014

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Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400

Nuclear engineering and design, 2016-03, Vol.298, p.33-40

2016

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Detailed evaluation of natural circulation mass flow rate in the annular gap between the outer reactor vessel wall and insulation under IVR-ERVC

Annals of nuclear energy, 2016-03, Vol.89, p.50-55

2016

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Evaluation of corium behavior in the lower plenum of the reactor vessel during a severe accident

Nuclear engineering and design, 2015-11, Vol.293, p.23-29

2015

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Effect of Subcooling on Pool Boiling of Water from Sintered Copper Microporous Coating at Different Orientations

Science and Technology of Nuclear Installations, 2018-01, Vol.2018, p.1-9

2018

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Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition

Nuclear Engineering and Technology, 2015, 47(1), , pp.66-73

2015

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In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor

Science and Technology of Nuclear Installations, 2018-01, Vol.2018, p.1-3

2018

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Detailed evaluation of melt pool configuration in the lower plenum of the APR1400 reactor vessel during severe accidents

Annals of nuclear energy, 2015-01, Vol.75, p.476-482

2015

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Corium melt researches at VESTA test facility

Nuclear Engineering and Technology, 2017, 49(7), , pp.1547-1554

2017

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Effect of heater orientation on pool boiling heat transfer from sintered copper microporous coating in saturated water

International journal of heat and mass transfer, 2016-12, Vol.103, p.277-284

2016

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Detailed evaluation of safety injection tank effects on in-vessel severe accident progression in a small break LOCA without safety injection

Annals of nuclear energy, 2013-08, Vol.58, p.54-59

2013

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Heat transfer to supercritical pressure carbon dioxide flowing upward through tubes and a narrow annulus passage

Progress in nuclear energy (New series), 2008-03, Vol.50 (2), p.518-525

2008

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An evaluation of a direct cooling method for the ex-vessel corium stabilization

Nuclear engineering and design, 2011-12, Vol.241 (12), p.4737-4744

2011

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Forced and mixed convection heat transfer to supercritical CO2 vertically flowing in a uniformly-heated circular tube

Convective heat transfer to CO2 at a supercritical pressure flowing vertically upward in tubes and an annular channel

Effect of a helical wire on mixed convection heat transfer to carbon dioxide in a vertical circular tube at supercritical pressures

Enhancement of Pool Boiling Heat Transfer in Water Using Sintered Copper Microporous Coatings

Experimental study on single- and two-phase flow behaviors within porous particle beds

NUMERICAL INVESTIGATION OF THE SPREADING AND HEAT TRANSFER CHARACTERISTICS OF EX-VESSEL CORE MELT

Development of safety injection flow map associated with target depressurization for effective severe accident management of OPR1000

Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART

Effectiveness and adverse effects of in-vessel retention strategies under a postulated SGTR accident of an OPR1000

Introduction of filtered containment venting system experimental facility in KAERI and results of aerosol test

Effectiveness and adverse effects of reactor coolant system depressurization strategy with various severe accident management guidance entry conditions for OPR1000

Pool boiling heat transfer of a copper microporous coating in borated water

Validation of RCS depressurization strategy and core coolability map for independent scenarios of SBLOCA, SBO, and TLOFW

Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400

Detailed evaluation of natural circulation mass flow rate in the annular gap between the outer reactor vessel wall and insulation under IVR-ERVC

Evaluation of corium behavior in the lower plenum of the reactor vessel during a severe accident

Effect of Subcooling on Pool Boiling of Water from Sintered Copper Microporous Coating at Different Orientations

Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition

In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor

Detailed evaluation of melt pool configuration in the lower plenum of the APR1400 reactor vessel during severe accidents

Corium melt researches at VESTA test facility

Effect of heater orientation on pool boiling heat transfer from sintered copper microporous coating in saturated water

Detailed evaluation of safety injection tank effects on in-vessel severe accident progression in a small break LOCA without safety injection

Heat transfer to supercritical pressure carbon dioxide flowing upward through tubes and a narrow annulus passage

An evaluation of a direct cooling method for the ex-vessel corium stabilization

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