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Song, Chul-Hwa(Professor)

INFO

  • AffiliationKorea Atomic Energy Research Institute
  • Majors Advanced Nuclear System Engineering
  • Contact Information042-868-8876
  • Major원자력공학
  • DegreePh.D.
  • Highest Level of Education한국과학기술원
  • E-Mail

Field of Research

Nuclear Reactor Safety Research

Research Results

-  C.-H. Song, “Challenging issues and recent R&D activities for enhancing nuclear safety in Korea”, Kern Technik, Vol.83, pp.1-5 (2018 -  C.-H. Song, “Some issues and challenges in advanced thermal-hydraulic safety research”, Nuclear Technology, Vol.196, pp. 421-445 (2016) -  N.H. Hoang, C.-H. Song*, I.C. Chu, D.J. Euh, “A novel semi-empirical correlation for wall heat transfer during saturated nucleate flow boiling”, J. Heat Transfer, Vol.140 (2018

Treatise

-  Effect of Flow Blockage on the Coolability during Reflood in a 2 × 2 Rod Bundle[Science and technology of nuclear installations,2014-04-01] -  Turbulent Mixing in a Rod Bundle with Vaned Spacer Grids: OECD/NEA-KAERI CFD Benchmark Exercise Test[Nuclear engineering and design,2014-05-08] -  A new method of relating a chord length distribution to a bubble size distribution for vertical bubbly flows[International J. Multiphase Flow,2015-07-01] -  Synthesis of the Turbulent Mixing in a Rod Bundle with Vaned Spacer Grids Based on the OECD-KAERI CFD Benchmark Exercise[Nuclear engineering and design,2014-03-17] -  Observation of critical heat flux mechanism in horizontal pool boiling of saturated water[Nuclear engineering and design,2014-03-31] -  RECENT IMPROVEMENTS IN THE CUPID CODE FOR A MULTI-DIMENSIONAL TWO-PHASE FLOW ANALYSIS OF NUCLEAR REACTOR COMPONENTS[Nuclear engineering and technology ,2014-07-09] -  QUANTITATIVE OBSERVATION OF CO-CURRENT STRATIFIED TWO-PHASE FLOW IN A HORIZONTAL RECTANGULAR CHANNEL[Nuclear engineering and technology ,2015-07-01] -  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] -  Study on the Optimal Heat Supply Control Algorithm for District Heating Distribution Network in Response to Outdoor Air Temperature[Energy,2015-05-16] -  ATLAS’ Contribution to Nuclear Safety[Nuclear engineering international,2015-06-01] -  Challenging issues and recent R&D activities for enhancing nuclear safety in Korea[KERNTECHNIK,2018-03-31] -  Improvements of COBRA-TF on the effect of flow blockage during a LB-LOCA with consideration of fuel relocation phenomenon[NUCLEAR ENGINEERING AND DESIGN,2017-12-31] -  A bubble dynamics-based model for wall heat partioning during nucleate flow boiling[INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER,2017-08-31] -  Experimental evaluation of local bubble parameters of subcooled boiling flow in a pressurized vertical annulus channel[NUCLEAR ENGINEERING AND DESIGN,2016-07-06] -  Some issues and challenges in advanced thermal-hydraulic safety research[NUCLEAR TECHNOLOGY,2016-07-31] -  A new method of relating a chord length distribution to a bubble size distribution for vertical bubbly flows,[INTERNATIONAL JOURNAL OF MULTIPHASE FLOW,2015-07-31]