Applicability of two-phase CFD to nuclear reactor thermalhydraulics and elaboration of Best Practice Guidelines-Reference-Cited by-同舟云学术

Applicability of two-phase CFD to nuclear reactor thermalhydraulics and elaboration of Best Practice Guidelines

Published:2012-12 Issue: Volume:253 Page:311-321
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Bestion D.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference25 articles.

1. Proceedings of the Workshop on Experiments and CFD Code Application to Nuclear Reactor Safety (XCFD4NRS);Anon,2008

2. A Validation Case for the NEPTUNE_CFD Platform: Instabilities in a Stratified Flow. Experimental, Theorethical and Code to Code Comparisons, NURETH-12;Bartosiewicz,2007

3. A first assessment of the NEPTUNE_CFD code: instabilities in a stratified flow, comparison between the VOF method and a two-field approach;Bartosiewicz;Int. J. Heat Fluid Flow,2008

4. Status and perspective of two-phase flow modelling in the NEPTUNE Multiscale thermal-hydraulic platform for nuclear reactor simulation;Bestion;Nucl. Eng. Technol.,2005

5. Extension of CFD Codes to Two-Phase Flow Safety Problems, NEA/SEN/SIN/AMA;Bestion,2006

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