The effect of the advanced drift-flux model of ASSERT-PV on critical heat flux, flow and void distributions in CANDU bundle subchannels

Author:

Hammouda N.,Rao Y.F.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Two-phase turbulent mixing and buoyancy drift in rod bundles;Carlucci;Nucl. Eng. Des.,2004

2. The drift flux model in the ASSERT subchannel code;Carver;Nucl. J. Canada,1987

3. Simulation of flow and phase distribution in vertical and horizontal bundles using the ASSERT subchannel code;Carver;Nucl. Eng. Des.,1990

4. Dix, 1970 Dix, G.E. 1970. Vapour void fraction for forced convection with subcooled boiling at low flow rates. General Electric Report, NEDO-10491.

5. Fortman, R.A., Hadaller, G.I., Hayes, R.C., Stern, F. 1997. Heat transfer studies with CANDU fuel simulators. In: The 5th International Conference on Nuclear Engineering (ICONE5), Nice, France.

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