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A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides

R. Ochoa, M. Vázquez, F. Álvarez-Velarde, F. Martín-Fuertes, N. García-Herranz, D. Cuervo

Ann. Nucl. Energy, vol: 57, num: , 32-40, published: 01 July 2013,


   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Calculation methods and computer codes.
            Monte-Carlo method.

   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.
      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 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.
         Fuel cycle.
            Transmutation of actinides, fission products and radioactive wastes in nuclear reactors.

   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Fuel cycle.
            Actinides production.

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