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Journal Articles

A Simplified Analytical Model for Estimation of the Initial Waterhammer Pressure and Force on a Circular Tube

Jong Chull Jo, Jae Jun Jeong, Frederick J. Moody

J. Pressure Vessel Technol. June 2021, 143(3): 034501.

Paper No: PVT-20-1055

DOI: https://doi.org/10.1115/1.4048421

Published Online: October 7, 2020

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Topics: Computational fluid dynamics, Pressure, Transients (Dynamics), Waves

Proceedings Papers

Effects of Initial Pressure and Length of a Broken Pipe on the Transient Hydraulic Loads Acting on Nuclear Steam Generator Tubes and Supports During Blowdown Following a Sudden Feedwater Pipe Break

Jong Chull Jo, Jae-Jun Jeong, Byong-Jo Yun

Proc. ASME. PVP2019, Volume 4: Fluid-Structure Interaction, V004T04A033, July 14–19, 2019

Paper No: PVP2019-93132

DOI: https://doi.org/10.1115/PVP2019-93132

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Topics: Feedwater, Nuclear reactor steam generators, Pipes, Pressure, Stress, Transients (Dynamics), Pressurized water reactors, Boilers, Flow (Dynamics), Unsteady flow

Journal Articles

Numerical Analysis of Subcooled Water Flashing Flow From a Pressurized Water Reactor Steam Generator Through an Abruptly Broken Main Feed Water Pipe

Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun, Jongkap Kim

J. Pressure Vessel Technol. August 2019, 141(4): 044501.

Paper No: PVT-18-1164

DOI: https://doi.org/10.1115/1.4043297

Published Online: April 25, 2019

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Topics: Feedwater, Flashing, Flow (Dynamics), Pipes, Pressure, Subcooling, Transients (Dynamics), Water, Numerical analysis, Computer simulation

Proceedings Papers

Prediction of Transient Hydrodynamic Loads on the PWR Steam Generator Tubes at a Main Feed Water Line Break Accident

Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun

Proc. ASME. PVP2018, Volume 4: Fluid-Structure Interaction, V004T04A019, July 15–20, 2018

Paper No: PVP2018-84152

DOI: https://doi.org/10.1115/PVP2018-84152

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Topics: Accidents, Boilers, Feedwater, Pressurized water reactors, Stress, Transients (Dynamics), Pipes, Computational fluid dynamics, Flow (Dynamics), Simulation

Proceedings Papers

Numerical Simulation of a Highly Compressed Saturated Water Flashing Flow

Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun, Frederick J. Moody

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A001, July 16–20, 2017

Paper No: PVP2017-65143

DOI: https://doi.org/10.1115/PVP2017-65143

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Topics: Computer simulation, Flashing, Flow (Dynamics), Water, Feedwater, Pipes, Accidents, Atmospheric pressure, Fluids, High pressure (Physics)

Journal Articles

Evaluation of a Numerical Analysis Model for the Transient Response of Nuclear Steam Generator Secondary Side to a Sudden Steam Line Break

Jong Chull Jo, Bok Ki Min, Jae Jun Jeong

J. Pressure Vessel Technol. June 2017, 139(3): 031305.

Paper No: PVT-16-1118

DOI: https://doi.org/10.1115/1.4035130

Published Online: December 1, 2016

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Topics: Disks, Numerical analysis, Pressure, Reservoirs, Rupture, Steam, Transients (Dynamics), Vacuum, Vapors, Flow (Dynamics)

Proceedings Papers

Validation of a CFD Analysis Model for the Thermal-Hydraulic Response of PWR Steam Generator to a Steam Line Break

Jong Chull Jo, Bok Ki Min, Jae Jun Jeong

Proc. ASME. PVP2016, Volume 4: Fluid-Structure Interaction, V004T04A010, July 17–21, 2016

Paper No: PVP2016-63048

DOI: https://doi.org/10.1115/PVP2016-63048

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Topics: Boilers, Computational fluid dynamics, Pressurized water reactors, Steam, Computer simulation, Transients (Dynamics), Flow (Dynamics), Heat transfer

Journal Articles

Transient Hydraulic Response of a Pressurized Water Reactor Steam Generator to a Feedwater Line Break Using the Nonflashing Liquid Flow Model

Jong Chull Jo, Jae Jun Jeong, Frederick J. Moody

J. Pressure Vessel Technol. June 2017, 139(3): 031302.

Paper No: PVT-16-1052

DOI: https://doi.org/10.1115/1.4034468

Published Online: October 11, 2016

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Topics: Computational fluid dynamics, Feedwater, Flow (Dynamics), Nozzles, Pressure, Transients (Dynamics), Water, Pressurized water reactors, Pipes, Waves

Journal Articles

Effects of a Venturi-Type Flow Restrictor on the Thermal-Hydraulic Response of the Secondary Side of a Pressurized Water Reactor Steam Generator to a Main Steam Line Break

Jong Chull Jo, Frederick J. Moody

J. Pressure Vessel Technol. August 2016, 138(4): 041304.

Paper No: PVT-15-1204

DOI: https://doi.org/10.1115/1.4032282

Published Online: April 28, 2016

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Topics: Flow (Dynamics), Pressure, Steam, Transients (Dynamics), Venturi tubes, Computational fluid dynamics, Pressurized water reactors

Proceedings Papers

Thermal-Hydraulic Response of the Secondary Side of a PWR Steam Generator With an Internal Structure to a Main Steam Line Break

Jong Chull Jo

Proc. ASME. PVP2015, Volume 4: Fluid-Structure Interaction, V004T04A052, July 19–23, 2015

Paper No: PVP2015-45092

DOI: https://doi.org/10.1115/PVP2015-45092

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Topics: Boilers, Pressurized water reactors, Steam, Pipes, Design, Dimensions, Failure, High cycle fatigue, Nozzles, Numerical analysis

Journal Articles

Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator Secondary Side to a Main Steam Line Break

Jong Chull Jo, Frederick J. Moody

J. Pressure Vessel Technol. August 2015, 137(4): 041301.

Paper No: PVT-14-1054

DOI: https://doi.org/10.1115/1.4028774

Published Online: August 1, 2015

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Topics: Pressure, Steam, Transients (Dynamics), Computational fluid dynamics, Fluids, Density

Proceedings Papers

Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator Secondary Side to a Main Steam Line Break

Jong Chull Jo, Frederick J. Moody

Proc. ASME. PVP2014, Volume 4: Fluid-Structure Interaction, V004T04A095, July 20–24, 2014

Paper No: PVP2014-28134

DOI: https://doi.org/10.1115/PVP2014-28134

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Topics: Nuclear reactor steam generators, Steam, Transients (Dynamics), Boilers, Accidents, Coolants, Pipes, Stress, Computational fluid dynamics, Dimensions

Journal Articles

Analytical Study of Flow Instability in a Natural Circulation Pressurized Water Reactor Auxiliary Feedwater System

Jong Chull Jo, Frederick J. Moody, Kyu Sik Do

J. Pressure Vessel Technol. April 2015, 137(2): 024501.

Paper No: PVT-14-1031

DOI: https://doi.org/10.1115/1.4027948

Published Online: October 15, 2014

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Topics: Condensed matter, Feedwater, Flow instability, Pressurized water reactors, Water, Momentum, Steam, Condensation, Flow (Dynamics)

Proceedings Papers

Numerical Analysis of Heat Transfer and Flow in a Passive Condensation Heat Exchanger

Jong Chull Jo, Kyu Sik Do, Yong Kab Lee

Proc. ASME. PVP2013, Volume 4: Fluid-Structure Interaction, V004T04A065, July 14–18, 2013

Paper No: PVP2013-97121

DOI: https://doi.org/10.1115/PVP2013-97121

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Topics: Condensation, Flow (Dynamics), Heat exchangers, Heat transfer, Numerical analysis, Boiling, Equilibrium (Physics), Fluids, Multiphase flow, Steam

Proceedings Papers

Analytical Study of Two-Phase Flow Instability in a Natural Circulation PWR Auxiliary Feedwater System

Jong Chull Jo, Frederick J. Moody, Kyu Sik Do

Proc. ASME. PVP2013, Volume 4: Fluid-Structure Interaction, V004T04A066, July 14–18, 2013

Paper No: PVP2013-97123

DOI: https://doi.org/10.1115/PVP2013-97123

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Topics: Feedwater, Pressurized water reactors, Two-phase flow, Water, Condensed matter, Steam, Pipes, Boilers, Buoyancy, Condensation

Proceedings Papers

Prediction of Potential for the Ingression of Crude Oil Covering the Sea Water Surface Into the Sea Water Cooling System of Nuclear Power Plant

Jong Chull Jo, Kyung Wan Roh, Hho Jhung Kim, Kyun Tae Kim

Proc. ASME. PVP2009, Volume 4: Fluid-Structure Interaction, 29-34, July 26–30, 2009

Paper No: PVP2009-77404

DOI: https://doi.org/10.1115/PVP2009-77404

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Topics: Cooling systems, Crude oil, Nuclear power stations, Seawater, Pumps, Cooling, Seas, Water, Computational fluid dynamics, Computer simulation

Proceedings Papers

Numerical Simulation of Pressure Transients in a PWR Main Steam Line System Due to Quick Operations of Pressure Relief Valve

Jong Chull Jo

Proc. ASME. PVP2009, Volume 4: Fluid-Structure Interaction, 35-43, July 26–30, 2009

Paper No: PVP2009-77410

DOI: https://doi.org/10.1115/PVP2009-77410

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Topics: Computer simulation, Pressure, Pressurized water reactors, Relief valves, Steam, Transients (Dynamics), Valves, High pressure (Physics), Damage, Deformation

Journal Articles

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

Jong Chull Jo, Dong Gu Kang

J. Pressure Vessel Technol. April 2010, 132(2): 021301.

DOI: https://doi.org/10.1115/1.4000727

Published Online: January 26, 2010

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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

Numerical Analysis of Unsteady Flow Field in the RWT for the Prediction of the Potential for Air Ingression Into the ECC Supply Lines During the SBLOCA at the KSNPs

Jong Chull Jo, Seon Oh Yu

Proc. ASME. PVP2007, Volume 4: Fluid-Structure Interaction, 569-577, July 22–26, 2007

Paper No: PVP2007-26504

DOI: https://doi.org/10.1115/PVP2007-26504

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Topics: Numerical analysis, Unsteady flow, Water, Valves, Pumps, Vortex flow, Computational fluid dynamics, Containment, Nuclear power stations, Accidents

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

Paper No: PVP2007-26507

DOI: https://doi.org/10.1115/PVP2007-26507

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Topics: Corrosion, Flow (Dynamics), Pipes, Computational fluid dynamics, Wall thickness, Feedwater, Shear stress

Journal citation

NARROW

A Simplified Analytical Model for Estimation of the Initial Waterhammer Pressure and Force on a Circular Tube

Effects of Initial Pressure and Length of a Broken Pipe on the Transient Hydraulic Loads Acting on Nuclear Steam Generator Tubes and Supports During Blowdown Following a Sudden Feedwater Pipe Break

Numerical Analysis of Subcooled Water Flashing Flow From a Pressurized Water Reactor Steam Generator Through an Abruptly Broken Main Feed Water Pipe

Prediction of Transient Hydrodynamic Loads on the PWR Steam Generator Tubes at a Main Feed Water Line Break Accident

Numerical Simulation of a Highly Compressed Saturated Water Flashing Flow

Evaluation of a Numerical Analysis Model for the Transient Response of Nuclear Steam Generator Secondary Side to a Sudden Steam Line Break

Validation of a CFD Analysis Model for the Thermal-Hydraulic Response of PWR Steam Generator to a Steam Line Break

Transient Hydraulic Response of a Pressurized Water Reactor Steam Generator to a Feedwater Line Break Using the Nonflashing Liquid Flow Model

Effects of a Venturi-Type Flow Restrictor on the Thermal-Hydraulic Response of the Secondary Side of a Pressurized Water Reactor Steam Generator to a Main Steam Line Break

Thermal-Hydraulic Response of the Secondary Side of a PWR Steam Generator With an Internal Structure to a Main Steam Line Break

Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator Secondary Side to a Main Steam Line Break

Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator Secondary Side to a Main Steam Line Break

Analytical Study of Flow Instability in a Natural Circulation Pressurized Water Reactor Auxiliary Feedwater System

Numerical Analysis of Heat Transfer and Flow in a Passive Condensation Heat Exchanger

Analytical Study of Two-Phase Flow Instability in a Natural Circulation PWR Auxiliary Feedwater System

Prediction of Potential for the Ingression of Crude Oil Covering the Sea Water Surface Into the Sea Water Cooling System of Nuclear Power Plant

Numerical Simulation of Pressure Transients in a PWR Main Steam Line System Due to Quick Operations of Pressure Relief Valve

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

Numerical Analysis of Unsteady Flow Field in the RWT for the Prediction of the Potential for Air Ingression Into the ECC Supply Lines During the SBLOCA at the KSNPs

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

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