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Преимущества быстрого реактора с усовершенствованной активной зоной в сравнении с проектом реактора БРЕСТ-300

В. Я. Гольдин, Г. А. Пестрякова

Мат. моделир., vol: 25, num: 10, 43-52, 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.
         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.
            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.
      Reactor and reactor installation dynamics. Control and direction.
         Controls and protection (theory, calculation, experiment).

   Nuclear reactor physics.
      Reactor and reactor installation dynamics. Control and direction.
         Reactor and nuclear power station control and safety methods and systems, passive safety systems (theory, calculation,experiment). Neutron field and energy generation control. Systems for in- and out-of-reactor control.

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