042-863-2290
Email: en2t@en2t.com
Room 213, R&D Building 2,
99 Gajeong-Ro, Yuseong-gu,
Daejeon, 34115, South Korea
May 30, 2023
CLEAN NUCLEAR ENERGY PROJECTS
| Date | Project Name |
|---|---|
| 2007-08 | Development of KNF Advanced Nuclear Fuel Export Strategy, KEPCO Nuclear Fuel |
| 2008-06 | System Dynamics Simulation of the Advanced Nuclear Fuel Export to USA, KEPCO Nuclear Fuel, Co. Ltd. |
| 2008-08 | Independent Review of the Advanced Design Features and Evaluation of APR1400 ECCS, Korea Hydraulic and Nuclear Power, Inc. |
| 2008-12 | Regulatory Nuclear Safe쇼 Analysis System code Development for Small and Medium Reactors, Korea Institute of Nuclear Safety |
| 2009-08 | Evaluation of Over Pressurization, Natural Circulation Cooling and Common Mode Failures of the SMART, Korea Atomic Energy Research Institute |
| 2009-11 | Development of TASS-SMR-VISA Program, Korea Atomic Energy Research Institute |
| 2010-03 | Evaluation of the Design Basis Safety Analysis for the Safety Evaluation of the Passive Residual Heat Removal System of the Advanced Reactors Korea Institute of Nuclear Safety |
| 2010-03 | Development of Thermal Hydraulic and Safety Database Management Program, Korea Atomic Energy Research Institute |
| 2010-04 | TRACE Simulation of ATLAS ISP-50, Korea Atomic Energy Research Institute |
| 2010-05 | Development of RELAP5//MOD3.3 Based Steam Generator Blowdown Load Analysis Code, Doosan Heavy Industries and Construction |
| 2010-05 | Development of TASS-SMR-VISA SMART NPA, Korea Atomic Energy Research Institute |
| 2010-07 | Development of Design Procedures and Licensing Documents for the Nuclear Export, KEPCO Nuclear Fuel |
| 2010-09 | Improvement of TASS/SMR Homogeneous and Equilibrium Models for SMART Safety Analysis, Korea Atomic Energy Research Institute |
| 2010-09 | Development of SMART Digital Transient Methodology, Korea Atomic Energy Research Institute |
| 2010-10 | DVI LIne SBLOCA 3-D Simulation of the ATLAS Facility using TRACE, Korea Atomic Energy Research Institute |
| 2011-02 | SMART Setpoint Analysis, Korea Atomic Energy Research Institute |
| 2011-03 | SMART MACCS2 Consequence Analysis, Korea Atomic Energy Research Institute |
| 2011-03 | Development of SMART Digital Core Protection and Monitoring Uncertainty Evaluation Modules, Korea Atomic Energy Research Institute |
| 2011-05 | Development of Scaling Methodology of CANDu6 Moderating System Test Facility, Korea Atomic Energy Research Institute |
| 2011-05 | Steam Generator Blowdown Load Analysis for Shin-Kori Nuclear Power Plants Units 5&6, Doosan Heavy Industries and Construction |
| 2011-07 | Development of Core Melt Analysis System Code for Severe Accident, Korea Atomic Energy Research Institute |
| 2011-07 | Technical Support for the Severe Accident VESTA Tests, Korea Atomic Energy Research Institute |
| 2011-08 | Improvement of CENTS Nuclear Plant Analyzer Module, KEPCO E&C |
| 2011-12 | Regulatory Evaluation Methods for the Safety Issue of the Non-Condensible Gas Accumulation in the ECCS, Korea Institute of Nuclear Safety |
| 2012-03 | Thermal Hydraulic Analysis of the ATLAS Integral Effect Tests, Korea Atomic Energy Research Institute |
| 2012-04 | Scaling Analysis of the VHTR Passive RCCS Performance Test Facility, Korea Atomic Energy Research Institute |
| 2012-05 | Development of Safety Analysis Methodology for the SFR Representative Design Basis Events, Korea Atomic Energy Research Institute |
| 2012-06 | Core Catcher Cooling Test Facility, Korea Atomic Energy Research Institute |
| 2012-06 | Thermal Hydraulic Safety Analysis and Evaluation of New Design Features of the Advanced PWR, Korea Institute of Nuclear Safety |
| 2012-07 | Enhancement of the TASS/SMR-S Model and Validation Analysis for the SMART Inherent Passive Safety Systems, Korea Atomic Energy Research Institute |
| 2012-11 | Design Development Report of the Optimum Passive RCCS Performance Test Rig for PMR200, Korea Atomic Energy Research Institute |
| 2013-03 | Thermal Hydraulic Analysis of the ATLAS Integral Effect Tests, Korea Atomic Energy Research Institute |
| 2013-07 | Safety Evaluation of the Advanced PWR New Design Features, Korea Institute of Nuclear Safety |
| 2013-07 | PGSFR MARS-LMR Steady State Input Calculation and Demonstration Safety Analysis for Selected SFR Design Basis Events, Korea Atomic Energy Research Institute |
| 2013-09 | Development of Core Molten Pool Behavior Model and Programing for Severe Accident Analysis, Korea Atomic Energy Research Institute |
| 2013-12 | Analysis of Core Catcher Cooling, Korea Atomic Energy Research Institute |
| 2014-03 | Safety Analysis for the ATLAS Beyond Design Basis Accident Tests, Korea Atomic Energy Research Institute |
| 2014-03 | Enhancement of the TASS/SMR-S Non-Equilibrium Two-phase Flow Model and Validation Analysis for the SMART Inherent Passive Safety Systems, Korea Atomic Energy Research Institute |
| 2014-05 | Accident-Tolerance Evaluation Model for the Dispersed FCM Nuclear Fuel Pellet in the Reactor Pressure Vessel during Severe Accident Conditions, Korea Atomic Energy Research Institute |
| 2014-06 | Development of Smart ATLAS Thermal Hydraulic Database Management Program Module, Korea Atomic Energy Research Institute |
| 2014-07 | Independent Regulatory Validation of the SPACE Code and LBLOCA Safety Analysis Methodology, Korea Institute of Nuclear Safety |
| 2014-07 | Evaluation of the Characteristics for the Main Steam Line Break Accident of the Advanced Reactor, Korea Institute of Nuclear Safety |