Implementation of a phenomenological DNB prediction model based on macroscale boiling flow processes in PWR fuel bundles-Reference-Cited by-同舟云学术

Implementation of a phenomenological DNB prediction model based on macroscale boiling flow processes in PWR fuel bundles

Published:2014-02 Issue: Volume:64 Page:176-190
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Mohitpour Maryam,Jahanfarnia Gholamreza,Shams Mehrzad

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference65 articles.

1. CFD prediction of flow and phase distribution in fuel assemblies with spacers;Anglart;Nucl. Eng. Des.,1997

2. Avramova, M., 2007. Development of an Innovative Spacer Grid Model Utilizing Computational Fluid Dynamics within a Subchannel Analysis Tool. PhD thesis, Pennsylvania State University.

3. Overview and discussion of the OECD/NRC benchmark based on NUPEC PWR subchannel and bundle tests;Avramova;Sci. Technol. Nucl. Install.,2013

4. Review of available data for validation of nuresim two-phase CFD software applied to CHF investigations;Bestion;Sci. Technol. Nucl. Install.,2008

5. Studies on burnout Part 3;Biasi;Energia Nucl.,1967

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