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Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE

Benjamin R. Betzler, Jeffrey J. Powers, Andrew Worrall

Ann. Nucl. Energy, vol: 101, num: 0, 489-503, published: 01 March 2017,


   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Designing, manufacturing and building-up reactor installations.

   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Fuel cycle.
            Fuel cycle schemes and parameters. Fuel cycle optimization.

   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.
            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.
            Computer codes. Expert systems. Data bases.

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