A. Research Projects
Development of World-Leading Full-Core Transport Numerical Reactor for Nuclear Design of Commercial Nuclear Power Plant (2019.04 - 2024.12)
Localization of In-core Nuclear Instrument Signal Measurement System with High Performance and Prompt Response Instrumentation based Technology Development (2020.05 - 2023.04)
Development of Key Technologies for Conceptual Design of Non-refueling Full-life Micro Reactor for Marine Applications (2019.04 - 2022.12)
IAEA CRP on Neutronics Benchmark of CEFR Start-Up Tests (2018.04 - 2022.12)
Development of operation supporting technology based on artificial intelligence for nuclear power plant start up and shutdown operation (2017.12 - 2022.11)
Development of high-performance 3D multiphysics computer code for reactor transient analysis (2019.03 - 2022.02)
Development of accident tolerance fuel utilization technology of integrated analysis platform (2020.01 - 2021.12)
Development of Lead-cooled Fast Reactor Technology (2017.04 - 2021.12)
Development of multi-physical safety analysis data compression code using PCA (2019.09 - 2021.08)
Development of AI Based Reactor Core Diagnostics System (2019.06 - 2021.05)
Evaluation of the rod-base core fuel characteristics for the high precision FFRD model (2020.08 - 2021.04)
Development of Multicycle Optimal Core Design Technology based on Simulation Annealing Method (2019.03 - 2021.02)
Development of High-Fidelity Multi-physics Computer Code Using Monte Carlo Method for PWR Analysis (2017.06 - 2020.05)
Development of Advanced Super-Critical Water-cooled Reactor and the Dedicated High Performance Computer System (2015.01 - 2020.02)
Establishment of a virtual-universial simulation platform for NPP systems (2018.02 - 2020.01)
Optimization Evaluation System Development for High Burnup Spent Nuclear Fuel Transportation/Storage Casks (2018.06 - 2019.12)
Safety evaluation system development for high burnup spent nuclear fuel Transportation/Storage casks (2018.07 - 2019.12)
크러드 침적 저감 피복관 및 미소셀 소결체 핵연료의 노심 핵적 특성 분석 (2018.09 - 2019.12)
Development of High Performance Three-Dimensional Neutron Transport Analysis Code (2016.11 - 2019.10)
Development and Coupling of Dynamic Reactor Core Nodal Computational Code and Nuclear Fuel Performance Analysis Code (2017.04 - 2019.09)
Assesment of Neutron Transport Methodology for Fast Reactor Application (2018.05 - 2018.12)
Development of Monitoring Equipment for Boron Concentration in Reactor Coolant (2015.09 - 2018.08)
Development of Neutron Transport and Kinetics Codes for Boron Free SMR (2014.03 - 2018.04)
Generation and Verification of Multi-group Cross Section Library of Lattice Physics Code for High Temperature (2017.02 - 2018.01)
Development and Analysis of Experimental Model for the Verification of Prototype Sodium-cooled Fast Reactor (2017.05 - 2017.12)
Depletion Benchmark Development for High-Fidelity Reactor Analysis (2014.12 - 2017.11)
Development of High Performance Monte Carlo Computer System for Light Water Reactor Whole Core Analysis (2014.06 - 2017.05)
Development of Advanced Long Life Small Modular Fast Reactor (2013.12 - 2016.11)
Development of Big Data Based Demonstration Platform to Improve the Safety of NPP (2014.12 - 2016.11)
Development of Resonance Treatment Method for VHTR Fuel (2015.03 - 2016.02)
Accuracy Enhancement of Neutron Transport Analysis by Improving Energy Resonance Self-Shielding Methods (2012.06 - 2015.05)
IAEA ADSR benchmark : kyoto university critical assembly - type A (2014.06 - 2015.05)
Accuracy Enhancement of Neutron Transport Alaysis by Improving Energy Resonance Self-Shielding Methods (2013.06 - 2015.05)
Establishment of Technology Supporting Foundations for Global Capability Enhancement of BOP in Nuclear Power Plants (2012.11 - 2015.04)
Future Nuclear Human Resource Development by Attending Advanced Nuclear Summer Schools (2013.06 - 2014.05)
Smart-grid based nuclear load-following operation technology (2011.06 - 2014.05)
Development of Advanced Reactor Core Analysis Code Employing Fusion Technique of Probabilistic Method and Deterministic Method (2011.05 - 2014.04)
Development of Ultra-long-life Core Fast Reactor (UCFR) Concept and Key Technology (2012.04 - 2014.03)
Basic research for Th cycle MSR development (2013.03 - 2014.02)
Summer School MeV, MIT NPS (2012.07 - 2013.05)
Premium Power Plant Design Requirements and Safety Research (2012.04 - 2013.05)
Feasibility Study of Daily Load Follow Operation for OPR1000 (2012.06 - 2013.02)
Summer School MeV, FJOH (2011.07 - 2012.07)