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Ki Yong CHOI(Professor)

INFO

  • AffiliationKorea Atomic Energy Research Institute
  • Majors Advanced Nuclear System Engineering
  • PositionChief major professor
  • Contact Information042-868-8928
  • Major원자력공학
  • DegreePh.D.
  • Highest Level of Education한국과학기술원
  • E-Mail

Field of Research

Nuclear Thermal-Hydraulic Safety, two-phase flow, heat transfer, system safety analysis, development of safety analysis code

Research Results

-  Ki Yong Choi and Hee Cheon No, "Experimental Studies of Flooding in Nearly Horizontal Pipes," Int. J. Multiphase Flow, V.21, No.3, pp419-436, 1995 -  Ki Yong Choi, H.S. Park, S. Cho,, D.J. Euh, Y.S. Kim, and W.P. Baek, "Integral Behavior of the ATLAS Facility for a 3-inch Small Break Loss of Coolant Accident," Nuclear Engineering and Technology, V.40, No.3, pp199-212, 2008 -  Ki Yong Choi, Yeon Sik Kim, Chul-Hwa Song, and Won-Pil Baek, “Major Achievements and Prospect of the ATLAS Integral Effect Tests,” Science and Technology of Nuclear Installations, Volume 2012, Article ID 375070, doi:10.1155/2012/375070, 2012.

Treatise

-  Comparison of Integral Thermal-Hydraulic Behaviors of a DVI Line Break SBLOCA with an Equivalent Cold Leg Break[Nuclear Engineering and Design,2014-07-01] -  Development of a Phenomena Identification Ranking Table for Simulating a Station Blackout Transient of a Pressurized Water Reactor with a Thermal-Hydraulic Integral Effect Test Facility[Annals of Nuclear Energy,2015-01-01] -  Safety Verification for the ECCS driven by the Electrically 4 Trains during LBLOCA Reflood Phase using ATLAS[Nuclear Engineering and Design,2014-10-01] -  MARS-KS Code and Sensitivity Analysis of a Pressure Wave Propagation Test Performed in the PMK-2 Test Facility[ NUCLEAR TECHNOLOGY,2015-08-01] -  An Analytical Investigation of Direct Vessel Injection Line Break Accidents of the ATLAS facility[ ANNALS OF NUCLEAR ENERGY,2015-04-10] -  An Analytical Investigation of Cold Leg Small Break Accidents of the ATLAS Facility[ NUCLEAR ENGINEERING AND DESIGN,2015-05-12] -  ATLAS' Contribution to Nuclear Safety[NUCLEAR ENGINEERING INTERNATIONAL,2015-06-01] -  The Characteristics of Break Flow of SBLOCA Tests in ATLAS Facility[ ANNALS OF NUCLEAR ENERGY,2015-08-14] -  ATLAS Program for Advanced Thermal-Hydraulic Safety Research[ NUCLEAR ENGINEERING AND DESIGN,2015-10-01] -  Comparison of Critical Flow Models for SBLOCA Tests of the ATLAS Facility[ ANNALS OF NUCLEAR ENERGY,2015-10-18] -  Systematic and Exact Scaling Analysis of the SIngle-Phase Natural Circulation Flow: The Hydraulic Similarity[PROGRESS IN NUCLEAR ENERGY,2016-02-01] -  A Theoretical Model for the Single-Phase Natural Circulatioin Flow Rate and Its Assessment Againg the ATLAS Test Data[PROGRESS IN NUCLEAR ENERGY,2017-02-01] -  Reflux Condensation Behavior in SBLOCA Tests of ATLAS Facility[ ANNALS OF NUCLEAR ENERGY,2017-02-02] -  Heat Transfer Scaling Analysis of the Single-Phase Natural Circulation Flow System[APPLIED THERMAL ENGINEERING,2017-07-01]