Experimental Study on Heat Dissipation of Spent Fuel Assembly of Sodium Fast Reactor During Defueling

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

Benchmark of CFD Methodology for Boron Dilution Simulation based on ROCOM Experiment

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

Experimental Investigation on Turbulence Flow Downstream a Spacer Grid with Split-Type Mixing Vanes in a 5x5 Rod Bundle Using PIV

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

Experimental Investigation on Spacer-Induced Cross Flow in a 5x5 Rod Bundle Using PIV

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

Numerical Simulation of Molten Fuel-Coolant Interacton with CosMetric

von Guo, Yuxiang
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 12 of 14 (2018)

ICONE29-91525 A Discrete-Ordinates Variational Nodal Method for Solving Multi-Dimensional Neutron Transport Equation With Unstructured Mesh

von Sun, Qizheng
Veröffentlicht in International Conference on Nuclear Engineering (29. : 2022 : Online) Proceedings of 2022 29th International Conference on Nuclear Engineering (ICONE 29) ; Volume 2: Nuclear fuel and material, reactor physics and transport theory, fuel cycle technology (2022)

Special section of the 7th Workshop on the CFD for Nuclear Reactor Safety (CFD4NRS-7)

Veröffentlicht 2019-2020