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인왕기 교수

In Wang Kee

INFO

  • 소속캠퍼스한국원자력연구원
  • 전공 신형원자력시스템공학
  • 연락처042-868-2823
  • 출신전공기계공학
  • 학위박사
  • 최종출신대학한국과학기술원
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연구분야

노심 열수력 실험 및 전산유체해석

Core Thermal Hydraulics Experiment and CFD Analysis

대표연구실적

-  Wang Kee In et al., Measurement and CFD calculation of spacer loss coefficient for a tight-lattice fuel bundle, Nuclear Engineering & Design 284, 2015 -  Wang-Kee In et al, Convective heat transfer of rod bundle flow with twist-vane spacer grid, Nuclear Engineering & Design 295, 2015 -  Chi Young Lee, Tae Hyun Chun, Wang Kee In, Effect of change in surface condition induced by oxidation on transient pool boiling heat transfer of vertical stainless steel and copper rodlets, Int. J. Heat & Mass Transfer 79, 2014

논문(최근 5년)

-  Measurement and CFD claculation of spacer loss coefficient for a tight-lattice fuel bundle[NED,2015-03-01] -  Transient pool boiling heat transfer during rapid cooling under saturated water condition[JNST,2015-05-01] -  Critical heat flux of oxidized zircaloy surface in saturated water pool boiling[JNST,2015-03-01] -  Effect of change in surface condition induced by oxidation on transient pool boiling heat transfer of vertical stainless steel and copper rodlets[IJHMT,2014-05-01] -  Prediction of water droplet evaporation on zircaloy surface[JNST,2014-06-01] -  Convective heat transfer experiment of rod bundle flow with twist-vane spacer grid[NED,2015-12-01] -  Augmentation of single phase forced convection heat transfer in tightly arrayed rod bundle with twist-vane spacer grid[EXPERIMENTAL THERMAL AND FLUID SCIENCE,2016-03-01]

특허(최근 5년)

-  Dual-cooled fuel rod's spacer grids ...[2015-09-15] -  이중냉각 환형 핵연료집합체용 하단고정체[2015-07-02] -  Unit spacer grid strap...[2014-04-08] -  Reverse conical lower end plug ...[2014-11-11] -  Truss reinforced spacer grid ...[2014-11-04] -  반사체 및 이를 포함하는 핵연료집합체[2017-07-17] -  지역난방공동주택 다중 열공급시스템 해석 프로그램[2018-06-11] -  Ensemble De Bouchon ....[2017-11-03]

연구과제 수행 실적

SMART 노심설계 고속로핵연료설계 사고저항성핵연료개발