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Pre-conceptual thermal–hydraulics and neutronics studies on sodium-cooled oxide and carbide cores

Luca Ammirabile, Haileyesus Tsige-Tamirat

Ann. Nucl. Energy, vol: 60 (2013), num: 0, Pages 127-140, published: 01 October 2013,


   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Reactors calculations.
            Intermediate and fast reactors.

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Reactors calculations.
            Calculations of neutron and gamma distributions, power generation, reaction rates, residual radioactivity and residual power generation.

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Reactors calculations.
            Calculation of critical parameters, reactivity coefficients and various reactivity effects.

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Reactors calculations.
            Calculations of fuel isotope composition changes (during fuel cycle and under postirradiation storage) and other fuel cycle parameters. Fuel management calculations. Calculations of radionuclides and actinides build-up.

   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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