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An Assessment of Void Fraction Data with COBRA-IE
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), Chicago, Illinois, August 30 - September 4, 2015


David L. Aumiller, Michael J. Meholic

Nucl. Sci. and Eng., vol: 184, num: 3, 453-462, published: 01 November 2016,


   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Thermohydraulics.
            Methods, codes and results of calculational and experimental analysis of temperature fields in materials and constructions, heat transfer and hydrodynamic parameters. Heat transfer intensification.

   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Thermohydraulics.
            Diagnostics and analysis of processes in coolants and moderators.

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