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Accuracy assessment of a new Monte Carlo based burnup computer code

B. El Bakkari, T. ElBardouni, B. Nacir, C. ElYounoussi, Y. Boulaich, O. Meroun, M. Zoubair, E. Chakir

Ann. Nucl. Energy, vol: 45, num: , 29-36, published: 04 July 2012,


   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.
            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.
         Calculation methods and computer codes.
            Computer codes. Expert systems. Data bases.

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Calculation methods and computer codes.
            Testing and comparing calculation methods, codes and nuclear data. Benchmark problems.

   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.
         Reactors calculations.
            Sensitivity of calculational results to variations of input data. Evaluation of calculation uncertainties.

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