Journal
6TH INTERNATIONAL CONFERENCE FRACTURE MECHANICS OF MATERIALS AND STRUCTURAL INTEGRITY (FMSI 2019)
Volume 16, Issue -, Pages 223-229Publisher
ELSEVIER SCIENCE BV
DOI: 10.1016/j.prostr.2019.07.045
Keywords
Reactor pressure vessels; structural integrity; IVR
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The results of experimental studies of material behaviour at different temperatures ranges and loading rates are presented in this paper. Using finite element method, an analysis of the influence of various factors on the integrity of the reactor vessel of the nuclear power plant under the action of the melted corium during a severe accident. The experimental data of special tests of the metal was used. In the part of experimental research, the characteristics of strength and high temperature creep for 15Kh2NMFA steel at temperatures typical of a severe accident were obtained. An estimation of the behaviour of high-temperature steel under conditions of exposure at temperature + 650 degrees C is carried out. New experimental data of steel deformation were obtained. Numerical simulation of the stress-strain state of the reactor vessel WWER-1000 under different conditions of a severe accident is presented. The variation of the residual wall thickness in the melting zone and different temperature of cooling of the outer surface of the vessel's wall were considered in the analysis. (C) 2019 The Authors. Published by Elsevier B.V.
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