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Proposed re-evaluation of the 154Eu thermal image capture cross-section based on spent fuel benchmarking studies

Steven E. Skutnik

Ann. Nucl. Energy, vol: 99, num: 0, Pages 80-107, published: 01 January 2017,


   Nuclear reactor physics.
      Neutron physics. Nuclear data.
         Neutron absorption (total absorption, radiative capture, activation, (n, p) and (n, α) reactions, capture gammas etc.).

   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.
            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.
            Methods and results of calculational analysis of integral experiments and methods and results of calculated reactor and shielding parameters specification by integral experiments and reactor operation.

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