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Dong Gu Kang
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Proceedings Papers

Assessment of APR-1400 Emergency Core Cooling System Performance for Design Basis LOCA Redefinition

Dong Gu Kang, Seung-Hoon Ahn, Soon Heung Chang, Byung-Gil Huh, Young-Seok Bang, Kwang-Won Seul
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A028, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30662
https://doi.org/10.1115/ICONE22-30662
View Paper titled, Assessment of APR-1400 Emergency Core Cooling System Performance for Design Basis LOCA Redefinition
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Topics: Design, Emergency core cooling systems, Accidents, Cooling, Diesel generators, Emergencies, Nuclear power stations, Plant design, Power uprate, Probabilistic safety assessment
Proceedings Papers

MARS-KS Calculations for ATLAS 6-Inch Cold Leg Break (SBLOCA) Test

Dong-Gu Kang, Joo-Sung Kim, Seung-Hoon Ahn
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 117-123, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54211
https://doi.org/10.1115/ICONE20-POWER2012-54211
View Paper titled, MARS-KS Calculations for ATLAS 6-Inch Cold Leg Break (SBLOCA) Test
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Topics: Accidents, Boilers, Cladding systems (Building), Condensation, Coolants, Errors, Flow (Dynamics), Pressure, Steady state, Temperature
Journal Articles

CFD Analysis of Thermally Stratified Flow and Conjugate Heat Transfer in a PWR Pressurizer Surgeline

Jong Chull Jo, Dong Gu Kang
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2010, 132(2): 021301.
https://doi.org/10.1115/1.4000727
Published Online: January 26, 2010
View Article titled, CFD Analysis of Thermally Stratified Flow and Conjugate Heat Transfer in a PWR Pressurizer Surgeline
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Topics: Computational fluid dynamics, Flow (Dynamics), Fluids, Heat transfer, Pipes, Stratified flow, Surges, Temperature, Transients (Dynamics), Pressurized water reactors
Proceedings Papers

Prediction of the Local Areas of CANDU Feeder Pipes Highly Susceptible to Wall Thinning Due to Flow-Accelerated Corrosion

Dong Gu Kang, Jong Chull Jo
Proc. ASME. PVP2007, Volume 4: Fluid-Structure Interaction, 579-589, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26507
https://doi.org/10.1115/PVP2007-26507
View Paper titled, Prediction of the Local Areas of CANDU Feeder Pipes Highly Susceptible to Wall Thinning Due to Flow-Accelerated Corrosion
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Topics: Corrosion, Flow (Dynamics), Pipes, Computational fluid dynamics, Wall thickness, Feedwater, Shear stress
Proceedings Papers

CFD Analysis of Thermally Stratified Flow and Heat Transfer in a PWR Pressurizer Surge Line

Dong Gu Kang, Jong Chull Jo
Proc. ASME. PVP2008, Volume 4: Fluid-Structure Interaction, 29-39, July 27–31, 2008
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61204
https://doi.org/10.1115/PVP2008-61204
View Paper titled, CFD Analysis of Thermally Stratified Flow and Heat Transfer in a PWR Pressurizer Surge Line
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Topics: Computational fluid dynamics, Heat transfer, Pressurized water reactors, Stratified flow, Surges, Pipes, Piping systems, Transients (Dynamics), Damage, Temperature distribution
Proceedings Papers

Numerical Calculation of Shear Stress Distribution on the Inner Wall Surface of CANDU Reactor Feeder Pipe Conveying Two-Phase Coolant

Jong Chull Jo, Dong Gu Kang, Kyung Wan Roh
Proc. ASME. IMECE2007, Volume 8: Heat Transfer, Fluid Flows, and Thermal Systems, Parts A and B, 1733-1744, November 11–15, 2007
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2007-41374
https://doi.org/10.1115/IMECE2007-41374
View Paper titled, Numerical Calculation of Shear Stress Distribution on the Inner Wall Surface of CANDU Reactor Feeder Pipe Conveying Two-Phase Coolant
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Topics: Coolants, Pipes, Shear stress, Computational fluid dynamics, Corrosion, Flow (Dynamics), Wall thickness, Feedwater, Fluids, Nuclear fuels
Journal Articles

Numerical Calculation of Shear Stress Distribution on the Inner Wall Surface of CANDU Reactor Feeder Pipe Conveying Two-Phase Coolant

Jong Chull Jo, Dong Gu Kang, Kyung Wan Roh
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2009, 131(2): 021301.
https://doi.org/10.1115/1.3008038
Published Online: December 10, 2008
View Article titled, Numerical Calculation of Shear Stress Distribution on the Inner Wall Surface of CANDU Reactor Feeder Pipe Conveying Two-Phase Coolant
Open the PDF for Numerical Calculation of Shear Stress Distribution on the Inner Wall Surface of CANDU Reactor Feeder Pipe Conveying Two-Phase Coolant in another window
Topics: Pipes