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Моделирование параметрических колебаний в системе охлаждения ядерных реакторов

Проскуряков К.Н.

Изв. вузов. Ядер. энерг., vol: , num: 3, 98-102, 119, published: , RU


   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Thermohydraulics.
            Methods, codes and results of calculational and experimental analysis of temperature fields in materials and constructions, heat transfer and hydrodynamic parameters. Heat transfer intensification.

   Nuclear reactor physics.
      Nuclear power. Reliability and safety problems. Engineering problems.
         Thermohydraulics.
            Diagnostics and analysis of processes in coolants and moderators.