Published October 2010 | Version v1
Journal article

A semi-empirical approach for predicting two-phase flow discharge through branches of various orientations connected to a horizontal main pipe

  • 1. Department of Nuclear Engineering, University of Palermo, Viale delle Scienze, 90128 Palermo (Italy)

Description

The subdivision of two-phase flow in branching conduits consisting of a large horizontal main pipe with upward, downward, or lateral branches of reduced diameter is of great interest in various technological fields. For example, these conduits are important in light-water nuclear reactors (LWRs) in the case of a small break loss-of-coolant accident (SBLOCA) in a leg of the reactor's primary coolant loops, as well as for breaks or valve malfunctions in a large pipeline. In these kinds of circumstances, the relevant phenomenology often involves phase stratification coupled with possible liquid entrainment or gas pool-through phenomena. Therefore, these phenomena were studied in depth to evaluate the pressure drop across conduit elements resulting from the redistribution of flow phases and the discharged mass among them. In the past, several experiments have been performed along with studies in flow modelling. As a result, several formulae and models for branch exit quality and consequent discharge mass flow rate predictions have been proposed. In recent years, we have been engaged in extensive research on this subject, resulting in a new semi-empirical formulation to express branch exit quality in terms of the physical processes taking place in the conduits, the operating parameters and the branch geometry. In this paper, we applied these correlations to representative sets of experiments previously reported in the literature, comprising a wide range of branch-to-main-pipe diameter ratios and operating pressures, which proved our formulation to be very accurate.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2010.05.016

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2010.05.016;
PII
S0029-5493(10)00341-9;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
240
Journal Issue
10
Journal Page Range
p. 2779-2788
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
4. international topical meeting on high temperature reactor technology
Acronym
HTR 2008
Dates
28 Sep - 1 Oct 2008
Place
Washington, DC (United States)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
42013298
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ENTRAINMENT; FLOW MODELS; FLOW RATE; LOSS OF COOLANT; PIPES; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; TWO-PHASE FLOW; VALVES; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY SYSTEMS; EQUIPMENT; FLOW REGULATORS; FLUID FLOW; MATHEMATICAL MODELS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TUBES

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.