Lateral Mixing Mechanisms in Vertical and Horizontal Interconnected Subchannel Two-Phase Flows

Author:

Gençay Sarman1,Teyssedou Alberto2,Tye Peter3

Affiliation:

1. Institute for Nuclear Engineering Technical University of Istanbul, Maslak, 80626 Istanbul, Turkey

2. École Polytechnique, Nuclear Engineering Institute Engineering Physics Department, 2900 Édouard-Montpetit Montréal, Québec H3T 1J4, Canada

3. Brais, Malouin and Associates, Inc., 5450 Côte-des-Neiges Suite 600, Montréal, Québec, Canada

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference21 articles.

1. D. S. ROWE, “COBRA III-C: A Digital Computer Program for Steady State and Transient Thermal Analysis of Rod Bundle Nuclear Fuel Elements,” BNWL-1695, Battelle Pacific Northwest Laboratory (1973).

2. Methods for Detailed Thermal and Hydraulic Analysis of Water-Cooled Reactors

3. An overview on rod-bundle thermal-hydraulic analysis

4. R. T. LAHEY, Jr., and J. F. MOODY, The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, American Nuclear Society, La Grange Park, Illinois (1984).

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