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주한규 Joo, Han-Gyu사진
  • 성명 주한규 Joo, Han-Gyu
  • 직위 교수
  • 학과 원자력시스템공학/ Nuclear Energy System Engineering
  • 전공 원자로물리, 전산해법
  • 사무실 연구실 : 원자로물리연구실
  • 홈페이지
  • 이메일
  • 연락처 Tel. 02-880-9241
학력 (Education)
1996 : Ph.D., Department of Nuclear Engineering, Purdue University, U.S.A.
1986 : M.S., Department of Nuclear Engineering, Seoul National University, Korea
1984 : B.S., Department of Nuclear Engineering, Seoul National University, Korea
경력 (Career)
2009.10 - Present Professor, Dept. of Nuclear Eng., Seoul National University
2004.08 - 2009.09 Associate Professor, Dept. of Nuclear Eng., Seoul National University
2002.09 - 2004.08 Principal Researcher, Reactor Engineering Department, Korea Atomic Energy
Research Institute(KAERI)
1998.06 - 2002.08 Senior Researcher, Reactor Engineering Department, KAERI
1997.08 - 1998.06 Post Doctoral Researcher, Dept. of Reactor Engineering, KAERI
1996.05 - 1997.07 Post Doctoral Research Associate, Dept. of Nuclear Engineering, Purdue University
1993.01 - 1996.05 Research Assistant, Dept. of Nuclear Engineering, Purdue University
1990.09 - 1992.12 Senior Researcher, Initial Core Design Department, KAERI
1986.02 - 1990.08 Researcher, Initial Core Design Department, KAERI
수상 및 영예 (Awards & Honors)
National Overseas Study Scholarship: Korean Government, 1993-1996
ANS Best Paper Award: ANS Reactor Physics Division, Winter Meeting, 1995
KNS Best Paper Award: KNS Fall Meeting, 1999
KNS Best Paper Award: KNS Spring Meeting, 2000
연구분야 (Research Interest)
Nuclear Reactor Neutron Transport: authored the DeCART high-fidelity direct whole core transport calculation code which is capable of generating subpin level power distributions for the whole core in one-step with the thermal-hydraulic feedback fully incorporated.

Reactor Kinetics: authored the initial version of the PARCS spatial kinetics code which has been a member of the NRC’s safety analysis code system and is being used worldwide. (

Neutronics-Thermal/Hydraulics Coupled Reactor Simulation: developed the RELAP/ PARCS and MARS/MASTER coupled code systems for integrated simulation of reactor kinetics and system thermal hydraulics; developed the Numerical Nuclear Reactor which performs high-fidelity, high-resolution, integrated simulation of nuclear reactors by the coupling the whole core neutron transport solutions and the ultra fine computational fluid dynamics (CFD) solutions.

Numerical Methods for Reactor Simulation: Nodal methods, Krylov subspace linear system solution methods, fuel loading optimization methods

Fusion Blanket Neutronics: Tritium breeding optimization, shielding analysis
최근 논문 (Paper)
- Han Gyu Joo, Gwan Young Kim, Leonid Pogosbekyan, “Subgroup Weight Generation Based on Shielded Pin-Cell?Cross Section Conservation,” Annals of Nuclear Energy, 36,859-868 (2009).
- Tong Kyu Park, Han Gyu Joo (Corresponding Author), Chang Hyo Kim and Hyun Chul Lee, “Multiobjective Loading Pattern Optimization by Simulated Annealing Employing Discontinuous Penalty Function and Screening Technique,”???Nucl. Sci. Eng., 162, 134-147 (2009).
- Han Gyu Joo, Joo Il Yoon, and Seung Gyu Baek. “Multigroup pin power reconstruction with two-dimensional?source expansion and corner flux discontinuity,”Annals of Nuclear Energy, 36, 85-97 (2009).
- Tae Young Han, Han Gyu Joo (Corresponding Author), Hyun Chul Lee and Chang Hyo Kim, “Multi-group unified nodal method with two-group coarse-mesh finite difference formulation,” Annals of Nuclear Energy, 35, 1975-1985 (2008).
- Jin Young Cho, Kang Seog Kim, Hyung Jin Shim, Jae Seung Song, Chung Chan Lee and Han Gyu Joo., “Whole core transport calculation employing hexagonal modular ray tracing and CMFD formulation,” Journal of Nuclear Science and Technology, 45, 740-751 (2008).


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