Development of a Droplet Entrainment Correlation for a Vertical Upward Annular-Mist Flow (KAERI)

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

Development of a Thermal Hydraulics Code for a Transient Two-Phase Flow Analysis in PWR Steam Generators

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

Thermal-Hydraulic Analysis for PWR Reactor Core in Subchannel Scale Using Component Analysis Code CUPID

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

A Three-Dimensional PWR LBLOCA Simulation Using the CUPID Code

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

A Three-Dimensional Multi-Physics Analysis of the Steam Line Break Accident of a PWR Using CUPID-RV/MASTER

von Lee, Jae Ryong
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 7 of 9 (2020)

Multi-Scale and Multi-Physics Nuclear Reactor Simulation for the Next Generation LWR Safety Analysis

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