Coupling functions: universal insights into dynamical interaction mechanisms
The dynamical systems found in nature are rarely isolated. Instead they interact and
influence each other. The coupling functions that connect them contain detailed information …
influence each other. The coupling functions that connect them contain detailed information …
Some thermal hydraulic challenges in sodium cooled fast reactors
D Tenchine - Nuclear Engineering and Design, 2010 - Elsevier
Sodium cooled fast reactors have been developed in France for nearly 50 years with
successively Rapsodie, Phenix and Superphenix plants. Thermal hydraulic challenges have …
successively Rapsodie, Phenix and Superphenix plants. Thermal hydraulic challenges have …
A functional subgrid drift velocity model for filtered drag prediction in dense fluidized bed
JF Parmentier, O Simonin, O Delsart - AIChE Journal, 2012 - Wiley Online Library
Due to computational time limitations, fully resolved simulations using the two‐fluid model of
the flow inside industrial‐scale fluidized beds are unaffordable. The filtered approach is …
the flow inside industrial‐scale fluidized beds are unaffordable. The filtered approach is …
CATHARE-3: A new system code for thermal-hydraulics in the context of the NEPTUNE project
P Emonot, A Souyri, JL Gandrille, F Barré - Nuclear Engineering and …, 2011 - Elsevier
After a thorough analysis of the industrial needs and of the limitations of current simulation
tools, EDF and CEA (Commissariat à l'Energie Atomique) launched the NEPTUNE Project in …
tools, EDF and CEA (Commissariat à l'Energie Atomique) launched the NEPTUNE Project in …
Implementation of an iterative solution procedure for multi-fluid gas–particle flow models on unstructured grids
A Passalacqua, RO Fox - Powder technology, 2011 - Elsevier
An iterative procedure for the solution of multi-fluid equations for gas–particle flows, with
kinetic theory closures and frictional stress models for the description of the particle phase is …
kinetic theory closures and frictional stress models for the description of the particle phase is …
The CUPID code development and assessment strategy
JJ Jeong, HY Yoon, IK Park, HK Cho - Nuclear Engineering and …, 2010 - koreascience.kr
A thermal-hydraulic code, named CUPID, has been being developed for the realistic
analysis of transient two-phase flows in nuclear reactor components. The CUPID code …
analysis of transient two-phase flows in nuclear reactor components. The CUPID code …
[HTML][HTML] Convective heat transfer modelling in dry-running polymer spur gears
V Roda-Casanova, F Sanchez-Marin… - International Journal of …, 2023 - Elsevier
Heat convection is an important phenomenon in the process of cooling polymer spur gears
running in dry conditions, which ultimately affects the strength of the gears. In order to gain …
running in dry conditions, which ultimately affects the strength of the gears. In order to gain …
A large interface model for two-phase CFD
P Coste - Nuclear Engineering and Design, 2013 - Elsevier
In the context of the Pressurized Thermal Shock (PTS) studies related to PWR life extension,
a two-phase CFD (Eulerian two-field 3D transient) approach has been developed and …
a two-phase CFD (Eulerian two-field 3D transient) approach has been developed and …
The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes
K Zhang - International Journal of Energy Research, 2020 - Wiley Online Library
Simulation is becoming increasingly important in the safety analysis of nuclear reactors
nowadays. The physical phenomena in a nuclear power plant happen on three classified …
nowadays. The physical phenomena in a nuclear power plant happen on three classified …
Applicability of two-phase CFD to nuclear reactor thermalhydraulics and elaboration of Best Practice Guidelines
D Bestion - Nuclear Engineering and Design, 2012 - Elsevier
Two-phase Computational Fluid Dynamics (CFD) is now increasingly applied to some
nuclear reactor thermalhydraulic investigations. A Writing Group of the OECD–NEA on the …
nuclear reactor thermalhydraulic investigations. A Writing Group of the OECD–NEA on the …