A Second-Order Turbulence Model Based on a Reynolds Stress Approach for Two-Phase Flow—Part I: Adiabatic Cases

Autor: S. Mimouni, F. Archambeau, M. Boucker, J. Laviéville, C. Morel

Publikováno v: Science and Technology of Nuclear Installations, Vol 2009 (2009)

In our work in 2008, we evaluated the aptitude of the code Neptune_CFD to reproduce the incidence of a structure topped by vanes on a boiling layer, within the framework of the Neptune project. The objective was to reproduce the main effects of the s

Externí odkaz: https://doaj.org/article/26d214a517464d89be012463913ee4df

A second order turbulence model based on a Reynolds stress approach for two-phase boiling flow. Part 1: Application to the ASU-annular channel case

Autor: Christophe Morel, F. Archambeau, M. Boucker, J. Laviéville, Stephane Mimouni

Publikováno v: Nuclear Engineering and Design. 240:2233-2243

High-thermal performance PWR (pressurized water reactor) spacer grids require both low pressure loss and high critical heat flux (CHF) properties. Numerical investigations on the effect of angles and position of mixing vanes and to understand in more

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::7ec1007aa2990f13f858fc0c1f124594
https://doi.org/10.1016/j.nucengdes.2009.11.019

NEPTUNE: A New Software Platform for Advanced Nuclear Thermal Hydraulics

Autor: Pascal Boudier, Eric Hervieu, Jean-Marc Hérard, Pierre Péturaud, D. Bestion, Philippe Fillion, Antoine Guelfi, Marc Grandotto, M. Boucker

Publikováno v: Nuclear Science and Engineering
Nuclear Science and Engineering, 2007, 156 (3), pp.281-324
Nuclear Science and Engineering, Academic Press, 2007, 156 (3), pp.281-324

The NEPTUNE project constitutes the thermal-hydraulic part of the long-term Electricite de France and Commissariat a l’Energie Atomique joint research and development program for the next generatio...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::67ed6ecc2cbae421b62256fb68cec242
https://doi.org/10.13182/nse05-98

Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA)

Autor: D. Bestion, Yury Egorov, H. Paillere, S. Willemsen, S. Pigny, M. Heitsch, M. Scheuerer, B. Hemström, Rolf Karlsson, Brian L. Smith, Michele Andreani, A. Martin, Eckhard Krepper, Florian R. Menter, G. Kimber, Mats Henriksson, Ismo Karppinen, I. Toth, M. Boucker, P. Muhlbauer

Publikováno v: Scheuerer, M, Heitsch, M, Menter, F, Egorov, Y, Toth, I, Bestion, D, Pigny, S, Paillere, H, Martin, A, Boucker, M, Krepper, E, Willemsen, S, Muhlbauer, P, Andreani, M, Smith, B, Karlsson, R, Henriksson, M, Hemstrom, B, Karppinen, I & Kimber, G 2005, ' Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA) ', Nuclear Engineering and Design, vol. 235, no. 2-4, pp. 359-368 . https://doi.org/10.1016/j.nucengdes.2004.08.049
Nuclear Engineering and Design 235(2005)2-4, 359-368

The objective of the ECORA project is the evaluation of computational fluid dynamics (CFD) software for reactor safety applications, resulting in best practice guidelines (BPG) for an efficient use of CFD for reactor safety problems. The project sche

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bf793aa37b22de9bd93ba99fb9fe69e8
https://doi.org/10.1016/j.nucengdes.2004.08.049

Euler-Euler Large Eddy Simulation of a Square Cross-Sectional Bubble Column Using the Neptune_CFD Code

Autor: M. Boucker, B. Ničeno, B. L. Smith

Publikováno v: Science and Technology of Nuclear Installations, Vol 2009 (2009)

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doajarticles::6fa2dbe4d3ba101dd1f4b1db2e591788
https://doaj.org/article/47267ce5b73340e6bb48f1b5a89b46a7