Condensation Heat Transfer of the Steam-Air Mixture on Bundle Heat Exchanger of PCCS (Passive Containment Cooling System)

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

Test Result and MARS-KS Calculation with Uncertainty Propagation Analysis for Pressurizer Surgeline IBLOCA

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

Plant Analysis of The OECD-ATLAS A5.1 Test

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

Simulation of a Prolonged Station Black Out Transient with RCP Seal Failures in Loop-2 of ATLAS

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

System Thermal-Hydraulics During SBO with a Passive Safety Feature of Hybrid SIT

von Cho, Seok
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 3 of 9 (2020)

Major Outcomes and Recommendations of the OECD-ATLAS Joint Project

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

Experimental Study on Investigation of Effect of Asymmetric Supply of Turbine-driven Auxiliary Feedwater during Station Blackout Transient of PWR

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