PSI - Issue 16

Andrii Kotliarenko et al. / Procedia Structural Integrity 16 (2019) 223–229 Andrii Kotliarenko et al. / Structural Integrity Procedia 00 (2019) 000 – 000

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The performed analysis of the stress-strain state of the reactor vessel with variation of the residual thickness of the vessel’s wall in the zone of melting and changing of the cooling temperature on the outer surface of the wall leads to the following conclusions: The level of stresses depends on the thermal conditions on the outer surface of the vessel’s wall and the residual wall thickness in the melting zone. The cooling temperature of the outer surface of the wall allows to control the level of stress and strain in the vessel’s wall in melting area. Estimation of the obtained experimental data and the features of deformation and fracture show the necessity for the future investigation of the behavior of material under a severe accident condition. Altstadt, E. and Mossner, T., 2000. Extension of the ANSYS creep and damage simulation capabilities. FZR, Dresden, pp. 296. Chirkov, A.Yu., 2012. Construction of two-level integration schemes for the equations of plasticity in the theory of deformation along the paths of small curvature. Strength of Materials 44 (6), 645 – 667. Loktionov, V.D., Mukhtarov, E.S., Yaroshenko, N.I., Orlov, V.E., 1999. Numerical investigation of the reactor pressure vessel behaviour under severe accident conditions taking into account the combined processes of the vessel creep and the molten pool natural convect ion. Nuclear Engineering and Design 191 (1), 31 – 52. Singh, B.K., Singh, R.J., Kumar, R., Baburajan, P.K., Rao, R.S., Gaikwad, Avinash, J., 2017. Coupled thermo-structural analysis for in-vessel retention in PHWR using ABAQUS. Nuclear Engineering and Design, 323, 407 – 416. Theofanous, T.G., Liu, C., Additon, S., Angelini, S., Kymäläinen, O., Salmassi, T., 1997. In -vessel coolability and retention of a core melt. Nuclear Engineering and Design 169 (1 – 3), 1 – 48. Tran, C.T., Kudinov, P., Dinh, T.N., 2010. An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head. Nuclear Engineering and Design 240 (9), 2148 – 2159. References