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Review of available data for validation of nuresim two-phase CFD software applied to CHF investigations
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.ORCID iD: 0000-0001-5595-1952
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2007 (English)In: Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, 2007Conference paper (Refereed)
Abstract [en]

The NURESIM Integrated Project of the 6th European Framework Program was envisaged to initiate the development of the next-generation common European Standard Software Platform for simulating nuclear reactors. The overall objective of NURESIM Thermalhydraulic sub-project is to improve the understanding and the predictive capabilities of the simulation tools for key two-phase flow thermal-hydraulic processes such as the Critical Heat Flux (CHF). A multi-scale analysis of reactor thermalhydraulics is envisaged and two-phase CFD is developed to allow some zoom on local processes when the resolution of system codes is not sufficient. Current industrial methods for CHF mainly use the sub-channel analysis and empirical CHF correlations based on large scale experiments having the real geometry of the reactor assembly. The NURESIM-TH activities regarding CHF aim at using two-phase CFD as a tool for understanding boiling flow processes, in order to subsequently help new fuel assembly design and to develop better CHF predictions in both PWR and BWR. A "Local Predictive Approach" may be envisaged for the long term where CHF empirical correlations would be based on local T/H parameters provided by CFD. This paper presents a review of existing experimental data bases which can be used for validation of the two-phase CFD application to Critical Heat Flux (CHF) investigations with respect to nuclear reactors. The phenomenology of DNB and Dry-Out are detailed identifying all basic flow processes which require a specific mode ling in CFD tool. The resulting program of work is given and the current state of the art of the modeling is presented.

Place, publisher, year, edition, pages
Keyword [en]
Computational fluid dynamics, Heat flux, Industrial applications, Nuclear reactors
National Category
Physical Sciences
URN: urn:nbn:se:kth:diva-155251ScopusID: 2-s2.0-44349113613ISBN: 0894480588ISBN: 978-089448058-4OAI: diva2:761012
12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, 30 September 2007 through 4 October 2007, Pittsburgh, PA, United States

QC 20141105

Available from: 2014-11-05 Created: 2014-11-04 Last updated: 2014-11-05Bibliographically approved

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