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Neutronic Analysis of the Oregon State TRIGA Reactor in Support of Conversion from HEU Fuel to LEU Fuel

M. R. Hartman, S. T. Keller, S. R. Reese, B. Robinson, J. Stevens, J. E. Matos, W. R. Marcum, T. S. Palmer, B. G. Woods

Nucl. Sci. and Eng., vol: 174, num: 2, 135-149, published: 01 June 2013,


   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.

   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.
            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 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.
            Research reactors.

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