OUR FACULTY

JI-HWAN HWANG

Combined M.S. and Ph.D Candidate (2017.03~)
E-mail skyjh0106@cau.ac.kr

Research Interest 

  • Reactor Vessel Exterior Cooling as a means of decay heat removal systems

  • Condensation in a vertical tube bundle geometry for Passive Containment Cooling System

 

Articles

  • Ji-Hwan Hwang and Dong-Wook Jerng, “A condensation heat transfer model with light gas effects in non-condensable gas mixtures.” International Communications in Heat and Mass Transfer, 130, 2022

  • Ji-Hwan Hwang and Dong-Wook Jerng, “An Improved Heat Transfer Model for Steam-Air Mixture Condensation with the Curvature Effect on Vertical Tubes.” International Communications in Heat and Mass Transfer, 123, 2021

  • Ji-Hwan Hwang, Min Ho Lee, In Cheol Bang and Dong-Wook Jerng, "A Numerical Study for Applicability of Water Tests to the Sodium Pool Natural Circulation Analysis", International Congress on Advances in Nuclear Power Plants (ICAPP 2018), April 8-11, 2018, Charlotte, NC, USA

  • Ji-Hwan Hwang, Eun-Hye Lee, Dong-Wook Jerng, "Investigations on the Steam Condensation in a Vertical Tube Geometry", International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), September 3-8, 2017, Xi'an, China 

  •  Ji-Hwan Hwang & Dong-Wook Jerng, “A study on steam condensation in presence of non-condensable gases at a vertical circular tube”, 6th Japan-Korea Joint Seminar on Nuclear Thermal Hydraulics and Safety for Students and Young Researchers (NTHAS), November 25-26, 2016, Nara, Japan

  • Dong-Wook Jerng & Ji-Hwan Hwang, “Investigations on Steam Condensation with Air at the Exterior Surface of a Circular Tube for Passive Containment Cooling System Design”, Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS), September 13-15, 2016, MIT, USA 

  • Ji-Hwan Hwang & Dong-Wook Jerng, "Investigations on the Steam Condensation in a Vertical Tube Geometry", Transactions of the Korean Nuclear Society Autumn Meeting, October 26-28, 2016, Gyeongju, Republic of Korea

GI-HYEON CHOI

Master's course (2019.02~)

 

Email choigh0930@cau.ac.kr

Research Interest 

  • Hydrogen risk analysis appeared by steam condensation at the end pipe of the filtered containment venting system

Articles 

  • Gi Hyeon Choi, Dong-Wook Jerng, and Tae Woon Kim, “Analyses of hydrogen risk in containment filtered venting system using MELCOR.” Nuclear Engineering and Technology, 54, 2022​

  • Gi-Hyeon Choi, Jea-Ho Park & Dong-Wook Jerng, "Condensation and Hydrogen Risk Calculations in FCVS Pipe with Python", Transactions of the Korean Nuclear Society Autumn Meeting, October 25-27, 2017, Gyeongju, Republic of Korea

RI-RA KIM

Administrator
E-mail rira0621@cau.ac.kr

JUNG-JIN BANG

Combined M.S. and Ph.D Candidate (2017.03~)

 

E-mail grwgr123@cau.ac.kr

Research Interest  

  • Study on steam condensation phenomena at the exterior surface of a tube bundle for operating NPP containment conditions

  • Research on the Concrete Type Containment Passive Cooling System Analysis

 

Articles 

  • Jungjin Bang, Gi Hyeon Choi, Dong-Wook Jerng, Sung-Won Bae, Sunghyon Jang, and Sang Jun Ha, “Analysis of steam generator tube rupture accidents for the development of mitigation strategies.” Nuclear Engineering and Technology, 54, 2022​

  • Jungjin Bang, Dong-Wook Jerng, and Han Gon Kim, “Comparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design.” Nuclear Engineering and Technology, 53, 2021

  • Jungjin Bang, Ji Hwan Hwang, Han Gon Kim, and Dong-Wook Jerng, “Parametric Analyses for the Design of a Closed-Loop Passive Containment Cooling System.” Nuclear Engineering and Technology, 53, 2021

  • Jung Jin Bang, and Dong-Wook Jerng, "Preliminary Analyses of Semi-Close Loop Passive Containment Cooling System", 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-9), May 15~18, 2019, Chongqing, China

  • Eun-Hye Lee, Hoe-Yeol Kim, Jungjin Bang, Dong-Wook Jerng and Tae Woon Kim, "Effects of the Operating Strategies of Filtered Containment Venting System on Cesium-137 Releases during Severe Accidents", Annals of Nuclear Energy (ANE), (Accepted) 

  • Hyun Jae Kim, Jung Jin Bang and Dong-Wook Jerng, "Analysis of Boiling Instability in Natural Circulation Conditions in Multiple Tube using the TRACE Code", Transactions of the Korean Nuclear Society Spring Meeting, May 17-18, 2018, Jeju, Republic of Korea 

  • Eun-Hye Lee, Wook-Jo Lee, Jung Jin Bang, and Dong-Wook Jerng, Sang Jun HA, "Comparison of SGTR Accident under Full-Power and Shut-Down Conditions", International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), September 3-8, 2017, Xi'an, China 

  • Hoe-Yeol Kim, Jung-Jin Bang and Dong-Wook Jerng, "Hydrogen distribution benchmark analysis using MELCOR for Nuclear Power Plant Safety Assessment", The 9th Asia-Pacific Power and Energy Engineering Conference (APPEEC2017), April 15-17, 2017, China

  • Jungjin Bang, Yujin Heo, Dong-wook Jerng "A study on the dependency between turbulent models and mesh configurations of CFD codes", Transactions of the Korean Nuclear Society Autumn Meeting, October 28-30, 2015, Gyeongju, Republic of Korea

  • Jungjin Bang, Ji Hwan Hwang, Han Gon Kim, and Dong-Wook Jerng, “Parametric Analyses for the Design of a Closed-Loop Passive Containment Cooling System.” Nuclear Engineering and Technology, xxx, 2020

Members

HYUN-JAE KIM

Master's course (2019.02~)
E-mail betterbbz@cau.ac.kr

Research Interest

  • Boiling instability of thermal multiple tube bundle

Articles

  • Hyun-Jae Kim, Dong-Wook Jerng, "Numerical Investigations of Two-phase Flow Instability in a Vertical Tube Bundle under Natural Convection Conditions", 16th Multiphase Flow Conference & Short Course, November 13-16, 2018, Dresden

  • Hyun Jae Kim, Jung Jin Bang and Dong-Wook Jerng, "Analysis of Boiling Instability in Natural Circulation Conditions in Multiple Tube using the TRACE Code", Transactions of the Korean Nuclear Society Spring Meeting, May 17-18, 2018, Jeju, Republic of Korea