Two-phase flow structure in large diameter pipes

► Local profiles of various quantities measured in large diameter pipe. ► Database for interfacial area in large pipes extended to churn-turbulent flow. ► Flow regime map confirms previous models for flow regime transitions. ► Data will be useful in developing interfacial area transport models for l...

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Veröffentlicht in:The International journal of heat and fluid flow 2012-02, Vol.33 (1), p.156-167
Hauptverfasser: Smith, T.R., Schlegel, J.P., Hibiki, T., Ishii, M.
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container_issue 1
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container_title The International journal of heat and fluid flow
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creator Smith, T.R.
Schlegel, J.P.
Hibiki, T.
Ishii, M.
description ► Local profiles of various quantities measured in large diameter pipe. ► Database for interfacial area in large pipes extended to churn-turbulent flow. ► Flow regime map confirms previous models for flow regime transitions. ► Data will be useful in developing interfacial area transport models for large pipes. Flow in large pipes is important in a wide variety of applications. In the nuclear industry in particular, understanding of flow in large diameter pipes is essential in predicting the behavior of reactor systems. This is especially true of natural circulation Boiling Water Reactor (BWR) designs, where a large-diameter chimney above the core provides the gravity head to drive circulation of the coolant through the reactor. The behavior of such reactors during transients and during normal operation will be predicted using advanced thermal–hydraulics analysis codes utilizing the two-fluid model. Essential to accurate two-fluid model calculations is reliable and accurate computation of the interfacial transfer terms. These interfacial transfer terms can be expressed as the product of one term describing the potential driving the transfer and a second term describing the available surface area for transfer, or interfacial area concentration. Currently, the interfacial area is predicted using flow regime dependent empirical correlations; however the interfacial area concentration is best computed through the use of the one-dimensional interfacial area transport equation (IATE). To facilitate the development of IATE source and sink term models in large-diameter pipes a fundamental understanding of the structure of the two-phase flow is essential. This understanding is improved through measurement of the local void fraction, interfacial area concentration and gas velocity profiles in pipes with diameters of 0.102m and 0.152m under a wide variety of flow conditions. Additionally, flow regime identification has been performed to evaluate the existing flow regime transition criteria for large pipes. This has provided a more extensive database for the development and evaluation of IATE source and sink models. The data shows the expected trends with some distortion in the transition region between cap-bubbly and churn-turbulent flow. The flow regime map for the 0.102m and 0.152m diameter test sections agree with the existing flow regime transition criteria. It may be necessary to perform further experiments in larger pipes and at higher gas flow rates to expand t
doi_str_mv 10.1016/j.ijheatfluidflow.2011.10.008
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Flow in large pipes is important in a wide variety of applications. In the nuclear industry in particular, understanding of flow in large diameter pipes is essential in predicting the behavior of reactor systems. This is especially true of natural circulation Boiling Water Reactor (BWR) designs, where a large-diameter chimney above the core provides the gravity head to drive circulation of the coolant through the reactor. The behavior of such reactors during transients and during normal operation will be predicted using advanced thermal–hydraulics analysis codes utilizing the two-fluid model. Essential to accurate two-fluid model calculations is reliable and accurate computation of the interfacial transfer terms. These interfacial transfer terms can be expressed as the product of one term describing the potential driving the transfer and a second term describing the available surface area for transfer, or interfacial area concentration. Currently, the interfacial area is predicted using flow regime dependent empirical correlations; however the interfacial area concentration is best computed through the use of the one-dimensional interfacial area transport equation (IATE). To facilitate the development of IATE source and sink term models in large-diameter pipes a fundamental understanding of the structure of the two-phase flow is essential. This understanding is improved through measurement of the local void fraction, interfacial area concentration and gas velocity profiles in pipes with diameters of 0.102m and 0.152m under a wide variety of flow conditions. Additionally, flow regime identification has been performed to evaluate the existing flow regime transition criteria for large pipes. This has provided a more extensive database for the development and evaluation of IATE source and sink models. 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Flow in large pipes is important in a wide variety of applications. In the nuclear industry in particular, understanding of flow in large diameter pipes is essential in predicting the behavior of reactor systems. This is especially true of natural circulation Boiling Water Reactor (BWR) designs, where a large-diameter chimney above the core provides the gravity head to drive circulation of the coolant through the reactor. The behavior of such reactors during transients and during normal operation will be predicted using advanced thermal–hydraulics analysis codes utilizing the two-fluid model. Essential to accurate two-fluid model calculations is reliable and accurate computation of the interfacial transfer terms. These interfacial transfer terms can be expressed as the product of one term describing the potential driving the transfer and a second term describing the available surface area for transfer, or interfacial area concentration. Currently, the interfacial area is predicted using flow regime dependent empirical correlations; however the interfacial area concentration is best computed through the use of the one-dimensional interfacial area transport equation (IATE). To facilitate the development of IATE source and sink term models in large-diameter pipes a fundamental understanding of the structure of the two-phase flow is essential. This understanding is improved through measurement of the local void fraction, interfacial area concentration and gas velocity profiles in pipes with diameters of 0.102m and 0.152m under a wide variety of flow conditions. Additionally, flow regime identification has been performed to evaluate the existing flow regime transition criteria for large pipes. This has provided a more extensive database for the development and evaluation of IATE source and sink models. The data shows the expected trends with some distortion in the transition region between cap-bubbly and churn-turbulent flow. The flow regime map for the 0.102m and 0.152m diameter test sections agree with the existing flow regime transition criteria. It may be necessary to perform further experiments in larger pipes and at higher gas flow rates to expand the range of conditions for which models can be developed and tested.</description><subject>Applied sciences</subject><subject>Circulation</subject><subject>Criteria</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Flow regime</subject><subject>Flows in ducts, channels, nozzles, and conduits</subject><subject>Fluid dynamics</subject><subject>Fundamental areas of phenomenology (including applications)</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Interfacial area</subject><subject>Large pipe</subject><subject>Mathematical models</subject><subject>Multiphase and particle-laden flows</subject><subject>Nonhomogeneous flows</subject><subject>Nuclear engineering</subject><subject>Nuclear power generation</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Physics</subject><subject>Pipe</subject><subject>Void fraction</subject><issn>0142-727X</issn><issn>1879-2278</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2012</creationdate><recordtype>article</recordtype><recordid>eNqNkDFPwzAQhS0EEqXwH7JUYkmwHcd2BwZUQUGqxFIkNsuxL9RRmgQ7oeLf46gVAxPTDe977-4eQguCM4IJv6szV-9AD1UzOls13SGjmJCoZRjLMzQjUixTSoU8RzNMGE0FFe-X6CqEGmPMMRMzhLeHLu13OkAyJSRh8KMZRg-Ja5NG-w9IrNN7GMAnveshXKOLSjcBbk5zjt6eHrer53Tzun5ZPWxSwzgdUs3ywtgSl5RTli9zXpBSYyGwtFZqJnBZUMFNURFtS8GIkKYyuTFWMkkly_M5uj3m9r77HCEMau-CgabRLXRjULGBJWfRWET0_oga34XgoVK9d3vtvyM0cVzV6k9TampqkmNT0b84rdLB6KbyujUu_IbQghPJ8-mk9ZGD-PeXA6-CcdAasM6DGZTt3D83_gDOR4eE</recordid><startdate>20120201</startdate><enddate>20120201</enddate><creator>Smith, T.R.</creator><creator>Schlegel, J.P.</creator><creator>Hibiki, T.</creator><creator>Ishii, M.</creator><general>Elsevier Inc</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>H8D</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20120201</creationdate><title>Two-phase flow structure in large diameter pipes</title><author>Smith, T.R. ; Schlegel, J.P. ; Hibiki, T. ; Ishii, M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c462t-a435cdb0b2624393651ba07708dd8a470b5276c5f1adb74178cfc3ccd84828433</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2012</creationdate><topic>Applied sciences</topic><topic>Circulation</topic><topic>Criteria</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Flow regime</topic><topic>Flows in ducts, channels, nozzles, and conduits</topic><topic>Fluid dynamics</topic><topic>Fundamental areas of phenomenology (including applications)</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Interfacial area</topic><topic>Large pipe</topic><topic>Mathematical models</topic><topic>Multiphase and particle-laden flows</topic><topic>Nonhomogeneous flows</topic><topic>Nuclear engineering</topic><topic>Nuclear power generation</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Physics</topic><topic>Pipe</topic><topic>Void fraction</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Smith, T.R.</creatorcontrib><creatorcontrib>Schlegel, J.P.</creatorcontrib><creatorcontrib>Hibiki, T.</creatorcontrib><creatorcontrib>Ishii, M.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Mechanical &amp; Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Aerospace Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>The International journal of heat and fluid flow</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Smith, T.R.</au><au>Schlegel, J.P.</au><au>Hibiki, T.</au><au>Ishii, M.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Two-phase flow structure in large diameter pipes</atitle><jtitle>The International journal of heat and fluid flow</jtitle><date>2012-02-01</date><risdate>2012</risdate><volume>33</volume><issue>1</issue><spage>156</spage><epage>167</epage><pages>156-167</pages><issn>0142-727X</issn><eissn>1879-2278</eissn><coden>IJHFD2</coden><abstract>► Local profiles of various quantities measured in large diameter pipe. ► Database for interfacial area in large pipes extended to churn-turbulent flow. ► Flow regime map confirms previous models for flow regime transitions. ► Data will be useful in developing interfacial area transport models for large pipes. Flow in large pipes is important in a wide variety of applications. In the nuclear industry in particular, understanding of flow in large diameter pipes is essential in predicting the behavior of reactor systems. This is especially true of natural circulation Boiling Water Reactor (BWR) designs, where a large-diameter chimney above the core provides the gravity head to drive circulation of the coolant through the reactor. The behavior of such reactors during transients and during normal operation will be predicted using advanced thermal–hydraulics analysis codes utilizing the two-fluid model. Essential to accurate two-fluid model calculations is reliable and accurate computation of the interfacial transfer terms. These interfacial transfer terms can be expressed as the product of one term describing the potential driving the transfer and a second term describing the available surface area for transfer, or interfacial area concentration. Currently, the interfacial area is predicted using flow regime dependent empirical correlations; however the interfacial area concentration is best computed through the use of the one-dimensional interfacial area transport equation (IATE). To facilitate the development of IATE source and sink term models in large-diameter pipes a fundamental understanding of the structure of the two-phase flow is essential. This understanding is improved through measurement of the local void fraction, interfacial area concentration and gas velocity profiles in pipes with diameters of 0.102m and 0.152m under a wide variety of flow conditions. Additionally, flow regime identification has been performed to evaluate the existing flow regime transition criteria for large pipes. This has provided a more extensive database for the development and evaluation of IATE source and sink models. The data shows the expected trends with some distortion in the transition region between cap-bubbly and churn-turbulent flow. The flow regime map for the 0.102m and 0.152m diameter test sections agree with the existing flow regime transition criteria. It may be necessary to perform further experiments in larger pipes and at higher gas flow rates to expand the range of conditions for which models can be developed and tested.</abstract><cop>New York, NY</cop><pub>Elsevier Inc</pub><doi>10.1016/j.ijheatfluidflow.2011.10.008</doi><tpages>12</tpages></addata></record>
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subjects Applied sciences
Circulation
Criteria
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Flow regime
Flows in ducts, channels, nozzles, and conduits
Fluid dynamics
Fundamental areas of phenomenology (including applications)
Installations for energy generation and conversion: thermal and electrical energy
Interfacial area
Large pipe
Mathematical models
Multiphase and particle-laden flows
Nonhomogeneous flows
Nuclear engineering
Nuclear power generation
Nuclear reactor components
Nuclear reactors
Physics
Pipe
Void fraction
title Two-phase flow structure in large diameter pipes
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