Abstract
Passive safety systems are an important feature of currently designed and constructed nuclear power plants. They operate independent of external power supply and manual interventions and are solely driven by thermal gradients and gravitational force. This brings up new needs for performance and reliably assessment. This paper provides a review on fundamental approaches to model and analyze the performance of passive heat removal systems exemplified for the passive heat removal chain of the KERENA boiling water reactor concept developed by Framatome. We discuss modelling concepts for one-dimensional system codes such as ATHLET, RELAP and TRACE and furthermore for computational fluid dynamics codes. Part I deals with numerical and experimental methods for modelling of condensation inside the emergency condensers and on the containment cooling condenser while part II deals with boiling and two-phase flow instabilities.
Highlights
Nuclear safety plays a central role in the design and operation of nuclear power plants
Thereby, we review numerical studies and developed heat transfer correlations for steam condensation used in one-dimensional system codes and in computational fluid dynamics codes (CFD)
Breber et al [29] stated that the Taitel and Dukler map is in good agreement with the condensation flow pattern data for tube diameters ranging from 8 mm to 22 mm, while for a tube diameter of 4.8 mm (Soliman’s [30] database) there is a large discrepancy due to negligence of surface tension effects
Summary
Amirhosein Moonesi Shabestary 1,2, * , Frances Viereckl 3 , Yu Zhang 4,5 , Rene Manthey 3 , Dirk Lucas 1 , Christoph Schuster 3 , Stephan Leyer 4 , Antonio Hurtado 3 and Uwe Hampel 1,2. Chair of Imaging Techniques in Energy and Process Engineering, Technische Universität Dresden, 01062 Dresden, Germany. Faculty of Science, Technology and Communication, University of Luxembourg, 4365 Luxembourg, Luxembourg. Received: 23 November 2019; Accepted: 17 December 2019; Published: 19 December 2019
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