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Capability Enhancement of MATRIX Electromagnetic Pump Analysis Code by Including Thermal Analysis

Ana Da Silva, Pradip Saha, Eric P. Loewen

Nucl. Technol., vol: 196, num: 1, 74-88, published: 01 October 2016,


   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Engineering problems (Thermodynamical cycles of nuclear power installations, out-core constructions, vessels, technological equipment, construction mechanics, nondestructive testing and acoustic diagnostics, equipment tests, corrosion etc.).

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Calculation methods and computer codes.
            Computer codes. Expert systems. Data bases.

   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.

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