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Neutronics and Depletion Methods for Multibatch Fluoride Salt-Cooled High-Temperature Reactors with Slab Fuel Geometry

Anselmo T. Cisneros, Dan Ilas

Nucl. Technol., vol: 183, num: 3, 331-340, published: 12 September 2013,


   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Nuclear energy and radiation utilization. Description and parameters of reactors, nuclear power stations and other nuclear installations.
            Desalination, technological and district heating installations.

   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Materials and constructions.
            Fuel elements and assemblies.

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Calculation methods and computer codes.
            Methods for solution of isotope kinetics problems and for calculation of fuel cycle parameters.

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

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