Abstract
Previous analytical results on flow splitting are generalized to consider multiple boiling channels systems. The analysis is consistent with the approximations usually adopted in the use of systems codes (like RELAP5 and TRACE5, among others) commonly applied to perform safety analyses of nuclear power plants. The problem is related to multiple, identical, parallel boiling channels, connected through common plena. A theoretical model limited in scope explains this flow splitting without reversal. The unified analysis performed and the confirmatory computational results found are summarized in this paper. New maps showing the zones where this behavior is predicted are also shown considering again twin pipes. Multiple pipe systems have been found not easily amenable for analytical analysis when dealing with more than four parallel pipes. However, the particular splitting found (flow along N pipes dividing in one standalone pipe flow plus N -1 identical pipe flows) has been verified up to fourteen pipes, involving calculations in systems with even and odd number of pipes using the RELAP5 systems thermal-hydraulics code.
Highlights
In nuclear power plants reactors, natural circulation is one of the mechanisms for decay heat removal after aHow to cite this paper: Lazarte, A.I. and Ferreri, J.C. (2016) Analytical and Computational Analysis of Flow Splitting in Multiple, Parallel Channels Systems
The main task is verifying whether those designs can avoid the development of instabilities in transients under nominal and postulated accident conditions or, important from the point of view of nuclear safety evaluations, that system codes used for such safety evaluations are capable of capturing the instabilities threshold
In a previous study, the present authors analyzed steady asymmetric flow splitting coming from static instabilities in thermodynamic conditions representative of a small break loss of coolant accident (SBLOCA) in an integral test facility (SEMISCALE) that have steam generators with two different pipes which, looking for results symmetry, were firstly considered identical with average height
Summary
In nuclear power plants reactors, natural circulation is one of the mechanisms for decay heat removal after a. In a previous study (see [4]), the present authors analyzed steady asymmetric flow splitting coming from static instabilities in thermodynamic conditions representative of a SBLOCA in an integral test facility (SEMISCALE) that have steam generators with two different pipes which, looking for results symmetry, were firstly considered identical with average height. This system configuration lead to non-symmetric flow splitting between the steam generator pipes. This is coherent with the previous results of the authors as shown in what follows
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