Numerical investigations on the coupling of the one-group interfacial area transport equation and subcooled boiling models for nuclear safety applications

Author:

Alali Abdullah,Schöffel Philipp J.,Herb Joachim,Macian Rafael

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference58 articles.

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2. Analysis of phase distribution in fully developed laminar bubbly two-phase flow;Antal;Int. J. Multiph. Flow,1991

3. Computational analysis of a subcooled boiling flow with a one-group interfacial area transport equation;Bae;J. Nucl. Sci. Technol.,2008

4. Analysis of subcooled boiling flow with one-group interfacial area transport equation and bubble lift-off model;Bae;Nucl. Eng. Des.,2010

5. Physical Model, Based on Bubble Detachment, and Calculation of Steam Voidage in the Subcooled Region of a Heated Channel;Bowring,1962

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