Professor
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Ser Gi HongProfessor
02) 2220-2365
hongsergi@hanyang.ac.kr
한양대학교 국제관(108) 404호
Education
BS : Hanyang University (1992), Nuclear Engineering
MS : KAIST (1994), Nuclear Engineering
PhD : KAIST (1999), Nuclear Engineering under Prof. N. Z. Cho
Professional Experiences
Post Doctor with Prof. N. Z. Cho : CARR (Center for Advanced Reactor Research)/KAIST : 1999.05 ~ 2000.08
Post Doctor with Prof. E. Greenspan : UC, Berkeley : 2004.03 ~ 2005.02
Lecturer (Nuclear Physics) : Kyung Hee University, Department Nuclear Engineering, 2003.09~2004.02
Principal Researcher : KAERI (Korea Atomic Energy Research Institute), 2001.04 ~ 2010.08
Senior Researcher : KAERI, 2010.09 ~ 2012.02
Associate Professor : Kyung Hee University, Department of Nuclear Engineering, 2012.03 ~ 2017.02
Professor : Kyung Hee University, Department of Nuclear Engineering, 2017.03 ~ 2020.02
Program Director (PD) for ABEEK : Kyung Hee University, Department of Nuclear Engineering, 2016.03 ~ 2017.02
Department Head : Kyung Hee University, Department of Nuclear Engineering, 2017.03 ~ 2019.02
Research Staff (Supervisory for Reactor Operation (SRO License)) : Research Reactor Center, Kyung Hee University, Department of Nuclear Engineering, 2012.03 ~ 2020.02
General Secretary of KNS (Korean Nuclear Society) : 2016.09 ~ 2017.08
Committee member of Computational Science and Reactor Physics Division : KNS, 2017 ~ Present
Professor : Hanyang University, Department of Nuclear Engineering, 2020.03 ~ Present
Department Head : Hanyang University, Department of Nuclear Engineering, 2021.03 ~ Present
Research Field
Development of advanced computational methods and codes for particle transport and reactor physics analysis
Parallel computations using LINUX clusters (Monte Carlo particle transport) for radiation transport and activation analysis for accelerators, reactor systems, and fusion facilities
Conceptual design of advanced reactor cores (PWRs, SMRs, Gen IV fast reactors)
Engineering design and analysis for criticality safety, radiation shielding, and activation
Development of multi-group cross-section generation method and library generation codes
Development of automatic source term generation code for spent fuel facilities
Development of computer code for fuel depletion and radiation source term analysis
Computer Code Development
Initial version of CRX MOC code (at KAIST)
Mathematical adjoint flux solver for AFEN2D code (at KAIST)
KARMA and its library generation programs (at KAERI with Dr. Kang-Seog Kim)
STRAUM (SN Transport for Radiation Analysis with Unstructured Meshes)
BESNA (Bateman Equation Solver for Nuclear Application)
MATXST (MATXS-based multi-group cross section generation for SN Transport)
AMORES (Automatic Multi-batch Origen Runner for Evaluation of Spent fuel)
Computational Method Development
Angular Dependent Rebalance (ADR) method
Infinite Green's function method for 1D slab multi-group discrete ordinates transport equation
Eigenfunction expansion Nodal method for 1D even-parity transport equation
Method of characteristic directional probabilities
3D AFEN (Analytic Function Expansion Nodal) method
Original method for ESSM (Embedded Self-Shielding Method)
LDEM-SCB (Linear Discontinuous Expansion Method with Sub-Cell Balances) for 3D SN transport with tetrahedral meshes
FMR acceleration for 3D linear discontinuous discretization of diffusion equation