CHF Correlation Development Under ERVC Conditions in Terms of Liquid Velocity

von Yoon, Jongwoong
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 11 of 14 (2018)

CFD Simulation of Condensation Heat Transfer in Horizontal Tubes

von Khasawneh, Khalid
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 2 of 9 (2020)

Experimental Analysis of the Flow Behavior in the Safety Injection Tank of APR1400

von Jeong, Woonho
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 11 of 14 (2018)

Observation of Air Bubble Characteristics by a Vertical Nozzle Under Pool Scrubbing Conditions

von Yoon, Jongwoong
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 1 of 9 (2020)

Pressurized Environments and Effect of Silica Gel Amount on Depressurization Inside the Containment

von Kam, Dong Hoon
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 4 of 9 (2020)

Application of Multi-Functional Nanoparticle to Nuclear Power Plant During Severe Accident Or Decontamination Process Using Its Magnetic Property

von Kam, Dong Hoon
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 12 of 14 (2018)

Dry Heat Rejection Technology by Direct Contact Heat Exchange for Waste Heat Removal System

von Moon, Jangsik
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 11 of 14 (2018)

Parametic Studies on CHF Trends for a Downward Facing Curved Geometry Under a Flow Condition

von Jung, Jun Yeong
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 7 of 9 (2020)

Safety Analyses of KAIST Micro Modular Reactor with Modified GAMMA+ Code

von Oh, Bong Seong
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 12 of 14 (2018)