Integrity Criteria for Models of RBMK Fuel-Channel Pipes under the Conditions of Accidental Heating

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Reasons for Unsealing and Post-Reactor State of Unsealed VVER and RBMK Fuel Elements

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Stochastic effects when determining the maximum RBMK channel power

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Assessment of the Vulnerability of RBMK Fuel Channels to Loads Produced by the Rupturing of One Channel

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Determination of the Fuel-Assembly Burnup in a Research Reactor by Repeated Short-Time Irradiation Followed by γ Spectrometric Measurements

By Bushuev A. V.   Kozhin A. F.   Li G.   Zubarev V. N.   Portnov A. A.   Alferov V. P.   Shchurovskaya M. V.  

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