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Изучение накопления урана-233 при облучении тория в реакторах с различными нейтронными спектрами

Гаджиев Г.И.\Сюзев В.Н.\Чистяков В.М.

Изв. вузов. Ядер. энерг., vol: 2006, num: 4, 32-35, 122, published: 01 January 2006,


   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Fuel cycle.
            Actinides production.

   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Fuel cycle.
            Fuel cycle schemes and parameters. Fuel cycle optimization.

   Nuclear reactor physics.
      Experimental investigations (methods, results, analysis).
         Thermal reactors. Experiments.

   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.