Professor
Tel: +82-52-217-2940
Major
Nuclear Reactor Physics; Reactor Core Design Analysis, and Methodology Development
Curriculum Vitae
2022~Present: Professor, UNIST
2016~2021: Associate Professor, UNIST
2011~2015: Assistant Professor, UNIST
2009~2011: R&D Staff, Oak Ridge National Laboratory
2005~2009: Senior Nuclear Engineer, Studsvik Scandpower Inc.,
1995~2000: Technical Staff, Korea Electric Power Research Institute
2003: Ph. D. Nuclear Engineering, Purdue University
1995: M. S. Nuclear Engineering, Seoul National University
1993: B. S. Nuclear Engineering, Seoul National University
Awards/Honors/Memberships
M&C 2017 Organization Committee
PHYSOR 2016 Organization Committee
Member, Joint Benchmark Committee of Mathematics and Computation, Reactor Physics, and Radiation & Shielding, American Nuclear Society, 2010~2012
Member, Reactor Physics Division Program Committee, American Nuclear Society, 2008~2011
Organization Committee for PHYSOR 2012 (Technical Program Co-chair)
Organization Committee for PHYSOR 2004 (Publication Committee)
The best paper award at ANS winter meeting, Washington, D.C., Nov. 2004
Research Interests
- Nuclear Reactor Physics
- Initial / Reload Reactor Core Design
- Steady State and Transient Core Analysis
- Resonance Treatment
- On-the-fly Doppler Broadening
- Safety Parameter Evaluations
- Neutron Cross Section Measurements
- Neutron Scattering Experiments
- Numerical Methods for Neutron Transport and Diffusion Analysis
- Monte Carlo Methods
- Method of Characteristics
- Unified Nodal Method
- Acceleration Techniques
- Advanced Reactor Designs
- Light Water Reactors
- Sodium-cooled Fast Reactors
- Molten Salt Reactors
- Small Modular Reactors
- High Temperature Gas-cooled Reactors
- High Performance Computing
- Parallel Computing by MPI and OpenMP
- Supercomputing
- Lattice Physics Code Development
- Monte Carlo Code
- Deterministic Transport Analysis Code
- Nodal Diffuion Transient Code
- Operation Support Packages
- Reactor Core Simulator
- Wester Services Company NPP simulator
- NEL macro-/micro- NPP simulator
- IAEA/KAERI NPP simulator
- Load Follow Opertion Simulator
Ongoing Research Topics
1. Development of MOC Transport code
- Multi-group Cross-Section Generation
- Pin-based pointwise energy slowing-down method
- Equivalence theory for structure material
- Resonance upscattering correction
- Enhanced neutron current method
- Resonance interference factor library method (option)
- Inflow transport correction
- Method of Characteristics
- T-Y optimum quadrature sets
- Assembly modular ray tracing method
- Direct neutron path linking method
- P0~P5
scattering source treatment
- Coarse mesh finite difference acceleration
- Matrix exponential method
- Chebyshev rational approximation method
- Chain with ~1400 isotopes
- Few-group Constants Generation
- Two-group cross-sections
- Critical spectrum with fundamental mode calculation
2. Development of 3D
Nodal Diffusion code
- Development of two-step approach reactor core design
code
- Nodal diffusion theory and pin-by-pin SP3 solver
steady/transient state calculation
- Engineering feature and multi-cycle calculation
capability for practical reactor core design
- High fidelity multi-scale multi-physics coupling with
TH subchannel, fuel performance, water chemistry, system codes for AOA/RIA analysis
- Advanced reactor core (SFR/VHTR/LWR/MSR) design and
analysis capability
- Development of real time reactor simulator
- Parallel computing capability for pin-by-pin
calculation
- Verification and Validation with IAEA ADS Benchmark,
Analysis of KUCA Experiments: Phase I
- Low-boron commercial PWR design
- Non-boron Small Modular PWR design
- Ultra-long Cycle Sodium Cooled Fast Reactor Design
- Long-life Lead Cooled Fast Reactor for Icebreacker
- Loading pattern search for long life mixed-cycle
operation in PWR
- Load Follow Operation Method development based on
Smart Grid
- Nuclear cross section library generation for fast
reactors simulation in deterministic code system
- IAEA-CRP CEFR Benchmark Problem Validation
- ABR-1000 core benchmark problem verification
5. Development of
Monte-Carlo code
- High fidelity multi-physics simulation (CTF, FRAPCON
etc.)
- Cross section processing with On The Fly (OTF) doppler
broadening
- Multi-group constant generation
- Generalized Perturbation Theory (GPT)
- Variance reduction technique
- Neutron/Gamma transport simulation
- Source term calculation
6. Multi-physics
coupling
- Development of multi-physics coupled reactor core
analysis code system
- Coupling with subchannel T/H codes
- Coupling with T/H system codes
- Coupling with fuel performance codes
- Coupling with water chemistry codes
- Nuclear reactor core safety analysis (RIA, LOCA etc.)
7. Sensitivity and
Uncertainty Analysis
- Sensitivity coefficient calculation for various
response functions such as the effective multiplication factor, reaction rate
ratios and bilinear ratios
- Uncertainty quantification as a function of covariance
data library
- Verification for UAM-LWR and UAM-SFR benchmark
8. AI &
Simulator
- AI training data generation using nuclear power plant
simulator
- Integrated code system for the safety analysis of
spent fuel storage cask