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Assessment of the traditional neutron-diffusion core-analysis method for the analysis of the Super Critical Water Reactor

W. Shen

Ann. Nucl. Energy, vol: 45, num: , 1-7, published: 04 July 2012,


   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 multidimensional problems.

   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.
            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.
            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.

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