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Simulation of mixed-oxide and low-enriched uranium fuel burnup in a pressurized water reactor and validation against distructive analysis results

Murphy B.D., Primm R.T., III

Nucl. Sci. and Eng., vol: 142, num: 3, 258-269, published: , US


   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.
         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.
         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.