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)

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)