교수진 검색

정범진 교수
- 최종학위
- 서울대학교 공학박사
- 연구분야
- 원자력안전, 열전달
학력
Ph.D., Seoul National University, Department of Nuclear Engineering, Korea, 1994.08
M.S., Seoul National University, Department of Nuclear Engineering, Korea, 1989.02
B.S, Seoul National University, Department of Nuclear Engineering, Korea, 1987.02
주요경력 및 활동
2013 – present, Full Professor, Kyung Hee University, Korea
2002 – 2013, Full Professor Jeju National University, Korea
2007 – 2008, Exchange Professor at INSPI (Innovative Nuclear Space Power and Propulsion Institute) & Department of Nuclear and Radiological Engineering, University of Florida, USA
2001 – 2002, Deputy Director of Nuclear Safety Division, Ministry of Science & Technology (MOST), Nuclear Power Plant Regulator, Korea
1999 – 2001, Visiting Research Fellow at Nuclear Engineering Research Group, School of Engineering, The University of Manchester, UK
1999 – 1999, Deputy Director of Strategic Technology Research & Development Division. MOST, R&D Planning and Management Officer in Nuclear Engineering and Aerospace Engineering, Korea
1997 – 1999, Deputy Director of Atomic Energy R&D Division, MOST, R&D Planning and Management Officer in Nuclear Field, Korea
1995 – 1997, Deputy Director of Nuclear Inspection & Enforcement Division, MOST, Nuclear Power Plant Regulator, Korea
1992 – 1992, Engineer at the Tain Engineers Ltd., Korea
Program Development and Operation of Nuclear Technology University Student Society (NtUss), Ministry of Science & Technology (MOST), 2002.12-2014.05
Development of Analogy Experiment Methodologies for HTGR, Ministry of Science & Technology (MOST), 2004.06-2006.03
SFR - AHX Scale Analysis Methodology Development, Ministry of Education, Science & Technology (MEST), 2010.03-2012.02
Amendments of Korean Regulatory Requirements including the IAEA DEC, Korea Institute of Nuclear Safety (KINGS), 2012.01-2012.11
Performance Improvement Study on the Passive Reactor Cavity Core Cooling System (RCCS), Ministry of Science, ICT and Future Planning (MSIP), 2013.03-2015.02
Nuclear Knowledge Succession Human Resources Development Team, Ministry of Education (MOE), 2013.09-2015.08
Study on the Legislation for the HLW R&D (High Level Waste Research and Development), Ministry of Education, Science & Technology (MEST), 2013.10-2015.02
Vitalization of Role and Function of KAIF(Korea Atomic Industry Folum), Ministry of Science, ICT and Future Planning (MSIP), 2013.11-2014.08
Analogy Experiments for IVR (In Vessel Retention) Phenomena, Ministry of Science, ICT and Future Planning (MSIP), 2014.06-2017.05
VHTR Mixed Convection Heat Transfer Experimental Research, Ministry of Science, ICT and Future Planning (MSIP), 2015.03-2017.02
Evaluation of the cooling performance of the IVR-ERVC and development of uncertainty assessment technology, Ministry of Science, ICT and Future Planning (MSIP), 2017.03-2021.12
Performance evaluation of the I-NERI Program and Development of Improvement Measures, Ministry of Science, ICT and Future Planning (MSIP), 2017.07-2017.12
Measurement of DHF(Dryout Heat Flux) of Self-heating Ex-Vessel Debris Bed, Ministry of Science, ICT and Future Planning (MSIP), 2017.07-2019.12
논문
G. U. Kang and B. J. Chung, 2012, "Effects of the Dimensions of Upward- and Downward-Facing Vertical Cavities on Natural Convection," International Communications in Heat and Mass Transfer, 39(3): 399-404.
B. J. Ko, M. H. Kim and B. J. Chung, 2012, "An Experimental Study on the Transition Criteria of Natural Convective Flows," Journal of Mechanical Science and Technology, 26(4): 1227-1234.
J. H. Heo and B. J. Chung, 2012, "Natural Convection Heat Transfer on the Outer Surface of Inclined Cylinders," Chemical Engineering Science, 73(7): 366-372.
J. H. Heo, M. S. Chae and B. J. Chung, 2013, "Influences of Vertical and Horizontal Pitches on the Natural Convection of Two Staggered Cylinders," International Journal of Heat and Mass Transfer, 57(1): 1-8.
J. Y. Moon and B. J. Chung, 2014, "Time-dependent Rayleigh-Benard convection: Cell formation and Nusselt number, " Nuclear Engineering and Design, 274(15): 146-153.
M. S. Chae and B. J. Chung, 2014, "Laminar Mixed Convection Experiments in Horizontal Pipes and Derivation of a Semi-empirical Buoyancy Coefficient," International Journal of Thermal Sciences, 84: 335-346.
C. K. Lim and B. J. Chung, 2015, "Natural Convection Experiments on the Upward and Downward Faces of Inclined Plates using an Electroplating System," Heat and Mass Transfer, 51(5): 713-722.
G. U. Kang and B. J. Chung, 2015, "Natural Convection Heat Transfer Characteristics within Vertical Cavities with Active and Inactive Top and Bottom Disks," International Journal of Heat and Mass Transfer, 87: 390-398.
M. S. Chae and B. J. Chung, 2015, "Chimney Effects depending on Height, Diameter and Prandtl Number," International Communications in Heat and Mass Transfer, 66: 196-202.
J. Y. Moon, J. H. Heo and B. J. Chung, 2015, "Influence of Chimney Widths on Natural Convection Cooling of a Vertical Finned Plate, " Nuclear Engineering and Design, 293: 503-509.
S. H .Hong and B .J. Chung, 2016, "Variations of the Optimal Fin Spacing according to Prandtl Number in Natural Convection, "International Journal of Thermal Sciences, 101: 1-8.
H. K. Park and B .J. Chung, 2016, "Mass Transfer Experiments for the Heat Load during In-Vessel Retention of Core Melt," Nuclear Engineering and Technology, 48: 906-914.
S. H. Kim and B. J. Chung, 2016, "Heat Load Imposed on Reactor Vessels during In-Vessel Retention of Core Melts," Nuclear Engineering and Design, 308: 1-8.
H. K. Park and B. J. Chung, 2016, "The Influence of Tip clearance and Prandtl Number on Turbulent Forced Convection Heat Transfer of Rectangular Fins," Heat and Mass Transfer, 52(12): 2759-2768.
S. M. Ohk and B. J. Chung, 2017, "Natural Convection Heat Transfer inside an Open Vertical Pipe: Influences of Length, Diameter and Prandtl Number," International Journal of Thermal Sciences, 115: 54-64.
S. H. Kim, H. K. Park and B. J. Chung, 2017, "Natural Convection of the Oxide Pool in a Three-Layer Configuration of Core Melts," Nuclear Engineering and Design, 317: 100-109.
H. K. Park, S. H. Kim and B. J. Chung, 2017, "Variation in the Angular Heat Flux of the Oxide Pool with Rayleigh number," Annals of Nuclear Energy, 107: 128-135.
학회활동
연구관심분야
Thermal hydraulic experiment and analysis related to the safety components of the nuclear system, Severe accident phenomena, Mixed convection heat transfer of the passive safety systems, Consultation of the nuclear policy, Nuclear manpower issues.
Professional Experience