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[en] The thermal stratification may lead an important role in the aging of the NPP piping because of the stresses caused by the temperature differences and cyclic temperature changes. Therefore it is for the strength analysis to point out the affected pipes, and the thermal hydraulic parameters of the stratified flow. For the investigation of the stratified flows the Computational Fluid Dynamics (CFD) codes provide an effective tool, with which the development and the breaking up of the stratification and the temperature distribution can be determined. The main difficulty of these CFD simulations is the uncertainty of the boundary conditions. In this paper some results of CFX simulations are presented concerning the pressurizer surge line, the primary loops and the inlet of the HPIS. The results show that the thermal hydraulic analysis of certain pipes can be performed with CFD simulations, but for determination of the boundary conditions further simulations with system codes, or measurements are required (Authors)
Source
Vidovszky, I. (ed.); VUJE, Inc., 918 64 Trnava (Slovakia); KFKI Atomic Energy Research Institute, Reactor Analysis Laboratory, H-1525 Budapest 114, POB 49 (Hungary); NPP Dukovany, 675 50 Dukovany (Czech Republic); Institute State Scientific and Technical Center for Nuclear and Radiation Safety, 35-37 Radgospna street, 03142 Kyiv-142 (Ukraine); Kozloduy NPP plc, Kozloduy 3321 (Bulgaria); Jaslovske Bohunice NPP (Slovakia); Nuclear Research Institute Rez plc, CZ-250 68 Husinec-Rez, cp.130 (Czech Republic); ALTA Dukovany, NPP Dukovany, 675 50 Dukovany (Czech Republic); Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest XI, Mueegyetem rkp. 9, 1111 (Hungary); International Atomic Energy Agency (IAEA), Wagramerstrasse 5, P.O.Box 100, A-1400 Vienna (Austria); 783 p; ISBN 963-372-632 8; 
; Nov 2005; p. 689-702; 15. Atomic Energy Research Symposium on WWER Reactor Physics and Reactor Safety; Znojmo (Czech Republic); 3-7 Oct 2005; Also available from VUJE, Inc., Okruzna 5, 918 64 Trnava (SK); 2 refs.; 24 figs.
; Nov 2005; p. 689-702; 15. Atomic Energy Research Symposium on WWER Reactor Physics and Reactor Safety; Znojmo (Czech Republic); 3-7 Oct 2005; Also available from VUJE, Inc., Okruzna 5, 918 64 Trnava (SK); 2 refs.; 24 figs.