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Feasibility study of U-235, Pu-239 and Pu-240 content determination in an irradiated fuel by neutron transmission analysis

Naguib K., Michaiel M.L., Morcos H.N.

Ann. Nucl. Energy, vol: 25, num: 11, 893-901, published: , GB


   Nuclear reactor physics.
      Experimental investigations (methods, results, analysis).
         Determination of fuel composition, fuel burn-up, fission products contents and distribution, changes of fuel composition during fuel cycle and under post-irradiation storage.

   Nuclear reactor physics.
      Experimental investigations (methods, results, analysis).
         Experimental techniques and methods. Planning of experiment and experimental data treatment.
            Planning of experiment and experimental data treatment (methods, means, codes, results).Corrections determination. Error analysis. Determination and taking into account of detector efficiency. Inverse problems solving.