Design Optimization of Supercritical CO, Brayton Cycle with Adjoint Method

von Son, Seongmin
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 6 of 14 (2018)

Performance Evaluation of Higher-order Numerical Scheme for Application of 1-D Nuclear System Analysis Code

von Lee, Wonwoong
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 7 of 14 (2018)

Adjoint-based Mesh Optimization Method: the Development and Application for Nuclear Fuel Analysis

von Son, Seongmin
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 9 of 14 (2018)

Preliminary Study of An Intelligent Autonomous Operation System for Nuclear Power Plant with Thermal-Hydraulic Analysis Code

von Kim, Min-Gil
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 10 of 14 (2018)

Feasibility Study of TES Integrated Nuclear Power Plant

von Lee, Ju Yeon
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 2 of 9 (2020)

Comparisons of Friction Models Implemented in U.S. TRACE and Korean MARS-KS System TH Codes

von Shin, Sung Gil
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 9 of 9 (2020)

A Preliminary Study of Thermal Oscillations Induced by Dryout in Printed Circuit Steam Generator (PCSG)

von Kwon, Jin Su
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 8 of 9 (2020)

Study of S-CO, Power Cycle for Water-Cooled SMR with a Desalination Capability

von Kwon, Jinsu
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 13 of 14 (2018)

Development of KAIST-STA(System Transient Analysis) Code and Verification Results for Transient Analyses of Supercritical CO2 Brayton Cycle

von Bae, Seong Jun
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 12 of 14 (2018)

Mesh Sensitivity Analysis of 1-D Nuclear System Analysis Code with Higher-Order Numerical Scheme

von Lee, Wonwoong
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 9 of 9 (2020)

Application of Adjoint Based Node Optimization Method to Nuclear Thermal-Hydraulic System Analysis Code

von Lee, Jae Jun
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 6 of 9 (2020)

GT2020-14880 Integration Options for Nuclear Steam Cycle Using Liquid Air Energy Storage

von Heo, Jin Young
Veröffentlicht in ASME Turbo Expo (2020 : Online) Proceedings of the ASME Turbo Expo 2020: Turbomachinery Technical Conference and Exposition - 2020 ; Volume 5: Controls, diagnostics, and instrumentation - cycle innovation - cycle innovations: energy storage (2020)

Sensitivity Analysis of Safety Injection Tanks for LOCA Scenarios

von Cho, Jai Oan
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 9 of 14 (2018)

Preliminary study of the conceptual design of the ATOM safety system

von Seo, Gwang Hyeok
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 2 of 14 (2018)

Safety Analyses of KAIST Micro Modular Reactor with Modified GAMMA+ Code

von Oh, Bong Seong
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 12 of 14 (2018)