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Kim, Kyung Doo(Professor)

INFO

  • AffiliationKorea Atomic Energy Research Institute
  • Majors Advanced Nuclear System Engineering
  • Contact Information042-868-2659
  • Major원자력공학
  • DegreePh.D.
  • Highest Level of EducationNorth Carolina State University
  • E-Mail

Field of Research

Nucelar Reactor Safety Analysis Code Development and Validation

Research Results

-  B.J. Kim, S.W. Lee, and K.D. Kim/ New wall drag and form loss models for one-dimensional dispersed two-phase flow/ Nuclear Science and Technology/2015. -  B.J. Kim, J.H. Kim, and K.D. Kim/Rayleigh-Taylor instability for thin viscous gas films: Application to critical heat flux and minimum film boiling/ International Journal of Heat and Mass Transfer / 2015. -  J. Heo, K. D. Kim/ PAPIRUS, a parallel computing framework for sensitivity analysis,uncertainty propagation, and estimation of parameter distribution/ Nucl. Eng. Design/2015

Treatise

-  On the wall drag term in the averaged momentum equation for dispersed flow[Nuclear Science and Engineering,2014-10-01] -  Rayleigh-Taylor instability for thin viscous gas films: Application to critical heat flux and minimum film boiling[International Journal of Heat and Mass Transfer,2014-08-01] -  Improvement of critical heat flux models for pool boiling on horizontal surfaces using interfacial instabilities of viscous potential flows[International Journal of Heat and Mass Transfer,2015-10-01] -  New wall drag and form loss models for one-dimensional dispersed two-phase flow[Nuclear Engineering and Technology,2015-01-05] -  PAPIRUS a parallel computing framework for sensitivity analysisuncertainty propagation and estimation of parameter distribution[Nuclear engineering and design,2015-07-02] -  Implementation of Data Assimilation Methodology for Physical Model Uncertainty Evaluation using Post-CHF Experimental Data[Nuclear Engineering and Technology,2014-10-01] -  Korean development of advanced thermal-hydraulic codes for water reactors and HTGRs: SPACE and GAMMA[Nuclear technology,2013-01-01] -  IDENTIFICATION OF TWO-DIMENSIONAL VOID PROFILE IN A LARGE SLAB GEOMETRY USING AN IMPEDANCE MEASUREMENT METHOD[Nuclear Engineering and Technology,2013-10-01]

Patent

-  원자로의 다목적 냉각장치[2013-08-26] -  배압식 노심보충수탱크 및 안전주입탱크 내의 응축억제장치[2014-11-13] -  MARS-SIM[2013-09-27] -  삼차원원전시뮬레이터버전1[2014-11-12] -  PAPIRUS-CA[2015-06-30] -  PAPIRUS-UQ[2015-06-30] -  PAPIRUS-DA[2015-06-30]