Subchannel Analysis of Mixed Convection in a Rod Bundle

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

Analysis of the Three Dimension Flow Field of Single and Multi-Span Fuel Assemblies

von Zhao, Hongji
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 5 of 14 (2018)

Numerical Simulation Investigation on Two-Phase Flow Instabilities in Two-Parallel-Channel

von Long, Jianping
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 5 of 9 (2020)

Numerical Investigation of Dryout Heat Flux and Heat Transfer Characteristics in Core Debris Bed of SFR after Serve Accident

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