Nuclear Reactor Physics; Reactor Core Design Analysis, and Methodology Development

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

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

- 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

- Matrix exponential method

- Chebyshev rational approximation method

- Chain with ~1400 isotopes

- Predictor/corrector

- 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