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Kyoung-Ho KANG(Professor)

INFO

  • AffiliationKorea Atomic Energy Research Institute
  • Majors Advanced Nuclear System Engineering
  • Contact Information042-868-2665
  • Major원자력 및 양자공학
  • DegreePh.D.
  • Highest Level of Education한국과학기술원
  • E-Mail

Field of Research

Nuclear Thermal-Hydraulics and Safety, Development of New Safety System, Critical Heat Flux, Safety Analysis

Research Results

-  강경호 외/Integral Effect Tests on Transient Thermal-Hydraulic Behavior during a Steam Generator Tube Rupture Accident in the APR1400/Nuclear Technology/2012년 3월 -  강경호 외/Separate and Integral Effect Tests for Validation of Cooling and Operational Performance of the APR+ Passive Auxiliary Feedwater System/Nuclear Engineering and Technology/2012년 8월 -  강경호 외/Experimental Study on the Heat Transfer Characteristics during the Pressure Transients under Supercritical Pressures/International Journal of Heat and Mass Transfer/2009년 6월

Treatise

-  Development of a new condensation model for the nearly-horizontal heat exchanger tube under the steam flowing conditions[International Journal of Heat and Mass Transfer,2014-12-01] -  An experimental study on layer inversion in the corium pool during a severe accident[Nuclear Engineering and Design,2014-10-01] -  Integral effect test and code analysis on the cooling performance of the PAFS (passive auxiliary feedwater system) during an FLB (feedwater line break) accident[Nuclear Engineering and Design,2014-08-01] -  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] -  Detailed evaluation of melt pool configuration in the lower plenum of the APR1400 reactor vessel during severe accidents[Annals of Nuclear Energy,2015-01-01] -  ATLAS program for advanced thermal-hydraulic safety research[ NUCLEAR ENGINEERING AND DESIGN,2015-12-01] -  Evaluation of corium behavior in the lower plenum of the reactor vessel during a severe accident[ NUCLEAR ENGINEERING AND DESIGN,2015-11-01] -  Application of direct passive residual heat removal system to the SMART reactor[ ANNALS OF NUCLEAR ENERGY,2016-03-01] -  Comparison of critical flow models for SBLOCA tests of the ATLAS facility[ ANNALS OF NUCLEAR ENERGY,2016-01-01] -  Reflux condensation behavior in SBLOCA tests of ATLAS facility[ ANNALS OF NUCLEAR ENERGY,2017-01-01] -  Overview of an investigation into SBLOCA tests of ATLAS facility[ ANNALS OF NUCLEAR ENERGY,2017-04-01] -  Evaluation of mechanistic wall condensation models for horizontal heat exchanger in PAFS (Passive Auxiliary Feedwater System)[ ANNALS OF NUCLEAR ENERGY,2017-09-01] -  Code assessment of ATLAS integral effect test simulating main steam-line break accident of an advanced pressurized water reactor[ JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY,2017-11-01]

Patent

-  LBLOCA 시 DVI 배관을 이용한 Blowdown 모의 방법[2015-05-26] -  아틀라스 열수력종합효과실험 데이터베이스 관리 시스템 (ATLAS SMART TH DB)[2017-07-13]