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Экономичный расчет многогруппового уравнения переноса нейтронов для пересчета усредненных по спектру сечений

Аристова Е.Н./Гольдин В.Я.

Мат. моделир., vol: 20, num: 11, 41-54, published: 16 November 2008,


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

   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.
            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.
      Reactor and reactor installation dynamics. Control and direction.
         Automation of reactor and reactor installation control. Automatic control systems.