2. Research >
A. Research Projects
| Project Start | Project End | Name |
|---|---|---|
| 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 |
| 2015.01 | 2020.29 | Development of Advanced Super-Critical Water-cooled Reactor and the Dedicated High Performance Computer System |
| 2018.02 | 2020.01 | Establishment of a virtual-universial simulation platform for NPP systems |
| 2018.05 | 2018.12 | Assesment of Neutron Transport Methodology for Fast Reactor Application |
| 2018.07 | 2019.12 | Safety evaluation system development for high burnup spent nuclear fuel transportation/storage casks |
| 2018.09 | 2019.05 | 크러드 침적 저감 피복관 및 미소셀 소결체 핵연료의 노심 핵적 특성 분석 |
| 2018.04 | 2022.12 | IAEA CRP on “Neutronics Benchmark of CEFR Start-Up Tests” |
32개 항목 표시