Nuclear Reactor Physics; Reactor Core Design Analysis, and Methodology Development
2016~Present: Associate Professor, UNIST2011~2015: Assistant Professor, UNIST2009~2011: R&D Staff, Oak Ridge National Laboratory2005~2009: Senior Nuclear Engineer, Studsvik Scandpower Inc.,1995~2000: Technical Staff, Korea Electric Power Research Institute2003: Ph. D. Nuclear Engineering, Purdue University1995: M. S. Nuclear Engineering, Seoul National University1993: B. S. Nuclear Engineering, Seoul National University
M&C 2017 Organization CommitteePHYSOR 2016 Organization CommitteeMember, Joint Benchmark Committee of Mathematics and Computation, Reactor Physics, and Radiation & Shielding, American Nuclear Society, 2010~2012Member, Reactor Physics Division Program Committee, American Nuclear Society, 2008~2011Organization 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
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
Transport Solver
- 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
Depletion
- Matrix exponential method
- Chebyshev rational approximation method
- Chain with ~1400 isotopes
- Predictor/corrector
Few-group Constants Generation
- Discontinuity factor
- 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
- 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- Cask analysis
- 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.)
- 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