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Miniature neutron source reactor burnup calculations using IRBURN code system

S.A.H. Feghhi, S. Jafarikia, F. Abtin

Ann. Nucl. Energy, vol: 47, num: , 242-248, published: 01 September 2012,


   Nuclear reactor physics.
      Experimental investigations (methods, results, analysis).
         Experimental techniques and methods. Planning of experiment and experimental data treatment.
            Particle sources.

   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Nuclear energy and radiation utilization. Description and parameters of reactors, nuclear power stations and other nuclear installations.
            Research and experimental reactors and assemblies.

   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Reactors calculations.
            Research 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.
      Theory and calculation of nuclear reactors and radiation transport.
         Calculation methods and computer codes.
            Computer codes. Expert systems. Data bases.

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