State-Of-The-Art CFD Assessment of Hydraulic Lift Force and Pressure Loss Coefficient for a Complete 16x16 PWR Fuel Spacer As Compared to the Traditional Empirical Approach

von Sheng, Dong-Yuan
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 3 of 14 (2018)

A Theoretical Model to Estimate the Fretting Damages Caused by Debris Particles on Fuel Rods - Coupling Work Rate Model and CFD/DEM Simulations

von Sheng, Dong-Yuan
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 7 of 14 (2018)

CFD Analysis of the Fluid Flow, Heat Transfer and Cladding Oxidation in a PWR Fuel Bundle

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

Investigations of Neutron Noise Induced by Transient Cross Flow in a PWR Reactor Core

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