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Comprehensive Analysis of Mechanical and Thermohydraulic Processes in the Graphite Masonry of Channel Rectors during an Accidental Rupture of a Fuel Channel

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Basic Problems of Experimental Studies of Accident and Transient Regimes of an RBMK Reactor on an Integrated Thermohydraulic Stand

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Expected Characteristics of the Multipurpose Pulsed Uranium–Graphite Reactor Complex

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Thermohydraulic studies of sodium-cooled reactor facilities

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