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)

Heat Loss Simulations in Large Scale Rod Bundle Tests

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

Comparison of the Effects of Different Types of Welding Nuggets

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

Uncertainty in Rod Bundle Mixing Test and Subchannel Analysis

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

Effect of Indirect Heating of Rod Bundle in Fuel Assembly Thermal Hydraulic Experiment on Local Heat Flux Measurement

von Han, Bin
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 1 of 9 (2020)

CFD Analysis on Mixing Vane Grid Performance in a 5x5 Rod Bundle

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

Numerical Study on the Effect of Grid Mixing Span in 2x1 Spacer Grid

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

Study on the Lateral Velocity and Vortex in Spacer Grid

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

Void Fraction Distribution and Code-to-code Comparison of Subcooled Boiling in a 5x5 Rod Bundle

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