2. Research‎ > ‎

A. Research Projects


26개 항목 표시
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2011.05 2014.04 Development of Advanced Reactor Core Analysis Code Employing Fusion Technique of Probabilistic Method and Deterministic Method 
2011.06 2014.05  Smart-grid based nuclear load-following operation technology 
2011.07 2012.07 Summer School MeV, FJOH 
2012.04 2014.03  Development of Ultra-long-life Core Fast Reactor (UCFR) Concept and Key Technology 
2012.04 2013.05 Premium Power Plant Design Requirements and Safety Research 
2012.06 2013.02 Feasibility Study of Daily Load Follow Operation for OPR1000 
2012.06 2015.05 Accuracy Enhancement of Neutron Transport Analysis by Improving Energy Resonance Self-Shielding Methods 
2012.07 2013.05 Summer School MeV, MIT NPS 
2012.11 2015.04  Establishment of Technology Supporting Foundations for Global Capability Enhancement of BOP in Nuclear Power Plants 
2013.03 2014.02 Basic research for Th cycle MSR development 
2013.06 2015.05 Accuracy Enhancement of Neutron Transport Alaysis by Improving Energy Resonance Self-Shielding Methods 
2013.06 2014.05 Future Nuclear Human Resource Development by Attending Advanced Nuclear Summer Schools 
2013.12 2016.11 Development of Advanced Long Life Small Modular Fast Reactor 
2014.03 2018.04 Development of Neutron Transport and Kinetics Codes for Boron Free SMR 
2014.06 2015.05  IAEA ADSR benchmark : kyoto university critical assembly - type A 
2014.06 2017.05 Development of High Performance Monte Carlo Computer System for Light Water Reactor Whole Core Analysis 
2014.12 2016.11 Development of Big Data Based Demonstration Platform to Improve the Safety of NPP 
2014.12 2017.11 Depletion Benchmark Development for High-Fidelity Reactor Analysis 
2015.03 2016.02 Development of Resonance Treatment Method for VHTR Fuel 
2015.09 2018.08 Development of Monitoring Equipment for Boron Concentration in Reactor Coolant 
2016.11 2019.10 Development of High Performance Three-Dimensional Neutron Transport Analysis Code 
2017.04 2021.12 Development of Lead-cooled Fast Reactor Technology 
2017.06 2020.05 Development of High-Fidelity Multi-physics Computer Code Using Monte Carlo Method for PWR Analysis 
2017.05 2017.12 Development and Analysis of Experimental Model for the Verification of Prototype Sodium-cooled Fast Reactor  
2017.04 2019.09 Development and Coupling of Dynamic Reactor Core Nodal Computational Code and Nuclear Fuel Performance Analysis Code 
2017.02 2018.01 Generation and Verification of Multi-group Cross Section Library of Lattice Physics Code for High Temperature  
26개 항목 표시
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