2017•Nuclear Engineering and DesignRequires access

Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 2. Creep deformation and failure of the reactor pressure vessel

V. D. Loktionov, E. S. Mukhtarov, I. V. Lyubashevskaya

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Key concepts: Corium, Reactor pressure vessel, VVER, Materials science, Creep, Heat transfer, Piping, Deformation (meteorology)

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Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 2. Creep deformation and failure of the reactor pressure vessel — Research Paper | ScholarLens