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Prediction of Liquid Film Dryout in Two-Phase Annular-Mist Flow in a Uniformly Heated Narrow Tube Development of Analytical Method under BWR Conditions

A method was developed based on the conservation lows to predict critical heat flux (CHF) causing liquid film dryout in two-phase annular-mist flow in a uniformly heated narrow tube under BWR conditions. The applicable range of the method is within the pressure of 3-9 MPa, mass flux of 500-2,000 kg/...

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Published in:Journal of nuclear science and technology 1998-09, Vol.35 (9), p.643-653
Main Authors: UTSUNO, Hideaki, KAMINAGA, Fumito
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cited_by cdi_FETCH-LOGICAL-c3280-2f0fca7f44a2f1f5a8b27e27c045549e3582860f7a93dba3c4ba9e879f5984da3
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description A method was developed based on the conservation lows to predict critical heat flux (CHF) causing liquid film dryout in two-phase annular-mist flow in a uniformly heated narrow tube under BWR conditions. The applicable range of the method is within the pressure of 3-9 MPa, mass flux of 500-2,000 kg/m 2 ·s, heat flux of 0.33-2.0 MW/m 2 and boiling length-to-tube diameter ratio of 200-800. The two-phase annular-mist flow was modeled with the three-fluid streams with liquid film, entrained droplets and gas flow. Governing equations of the method are mass continuity and energy conservation on the three-fluid streams. Constitutive equations on the mass transfer which consist of the entrainment fraction at equilibrium and the mass transfer coefficient were newly proposed in this study. Confirmation of the present method were performed in comparison with the available film flow measurements and various CHF data from experiments in uniformly heated narrow tubes under high pressure steam- water conditions. In the heat flux range (q"
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In the heat flux range (q"&lt;2MW/m 2 ) practical for a BWR, agreement of the present method with CHF data was obtained as, (Averaged ratio)±(Standard deviation)=0.984±0.077, which was shown to be the same or better agreement than the widely-used CHF correlations.</description><identifier>ISSN: 0022-3131</identifier><identifier>EISSN: 1881-1248</identifier><identifier>DOI: 10.1080/18811248.1998.9733920</identifier><identifier>CODEN: JNSTAX</identifier><language>eng</language><publisher>Tokyo: Taylor &amp; Francis</publisher><subject>annular-mist flow ; Applied sciences ; BWR type reactors ; critical heat flux ; deposition ; droplets ; Energy ; Energy. 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In the heat flux range (q"&lt;2MW/m 2 ) practical for a BWR, agreement of the present method with CHF data was obtained as, (Averaged ratio)±(Standard deviation)=0.984±0.077, which was shown to be the same or better agreement than the widely-used CHF correlations.</description><subject>annular-mist flow</subject><subject>Applied sciences</subject><subject>BWR type reactors</subject><subject>critical heat flux</subject><subject>deposition</subject><subject>droplets</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>entrainment</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>heated tube</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>liquid film dryout</subject><subject>three-fluid streams</subject><subject>tight lattice</subject><issn>0022-3131</issn><issn>1881-1248</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>1998</creationdate><recordtype>article</recordtype><recordid>eNp9UV1r2zAUFWWDZt1-QkGwvTrTl23pbVm6rIV0KyOlj-bGlqiKIqWS3OBfsr87m6T0bU-Xe8859-sgdEnJnBJJvlIpKWVCzqlScq5qzhUjZ2g21YsJeIdmhDBWcMrpOfqQ0tOYVqKSM_T3LurOttkGj4PBa_vc2w6vrNvhqziEPmPr8eYQirtHSBovvO8dxOLWpoxXLhwmGPC9tybEnRvwtYasO_wLYhzBTb_V-Eq_aBf2O-3zNGLhwQ3ZtuDwrc6PocO973TE3x_-4GXwnZ12SR_RewMu6U-neIHuVz82y-ti_fvnzXKxLlrOJCmYIaaF2ggBzFBTgtyyWrO6JaIshdK8lExWxNSgeLcF3ootKC1rZUolRQf8An0-9t3H8NzrlJun0MdxxdRQUVdKMCnoyCqPrDaGlKI2zT7aHcShoaSZPGhePWgmD5qTB6Puy6k7pPFgE8G3Nr2Jq7IkSoy0b0ea9dMb4RCi65oMgwvxVcP_P-kfygCbZQ</recordid><startdate>19980901</startdate><enddate>19980901</enddate><creator>UTSUNO, Hideaki</creator><creator>KAMINAGA, Fumito</creator><general>Taylor &amp; Francis</general><general>Atomic Energy Society of Japan</general><general>Taylor &amp; Francis Ltd</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope></search><sort><creationdate>19980901</creationdate><title>Prediction of Liquid Film Dryout in Two-Phase Annular-Mist Flow in a Uniformly Heated Narrow Tube Development of Analytical Method under BWR Conditions</title><author>UTSUNO, Hideaki ; KAMINAGA, Fumito</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c3280-2f0fca7f44a2f1f5a8b27e27c045549e3582860f7a93dba3c4ba9e879f5984da3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1998</creationdate><topic>annular-mist flow</topic><topic>Applied sciences</topic><topic>BWR type reactors</topic><topic>critical heat flux</topic><topic>deposition</topic><topic>droplets</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>entrainment</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>heated tube</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>liquid film dryout</topic><topic>three-fluid streams</topic><topic>tight lattice</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>UTSUNO, Hideaki</creatorcontrib><creatorcontrib>KAMINAGA, Fumito</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><jtitle>Journal of nuclear science and technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>UTSUNO, Hideaki</au><au>KAMINAGA, Fumito</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Prediction of Liquid Film Dryout in Two-Phase Annular-Mist Flow in a Uniformly Heated Narrow Tube Development of Analytical Method under BWR Conditions</atitle><jtitle>Journal of nuclear science and technology</jtitle><date>1998-09-01</date><risdate>1998</risdate><volume>35</volume><issue>9</issue><spage>643</spage><epage>653</epage><pages>643-653</pages><issn>0022-3131</issn><eissn>1881-1248</eissn><coden>JNSTAX</coden><abstract>A method was developed based on the conservation lows to predict critical heat flux (CHF) causing liquid film dryout in two-phase annular-mist flow in a uniformly heated narrow tube under BWR conditions. 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In the heat flux range (q"&lt;2MW/m 2 ) practical for a BWR, agreement of the present method with CHF data was obtained as, (Averaged ratio)±(Standard deviation)=0.984±0.077, which was shown to be the same or better agreement than the widely-used CHF correlations.</abstract><cop>Tokyo</cop><pub>Taylor &amp; Francis</pub><doi>10.1080/18811248.1998.9733920</doi><tpages>11</tpages><oa>free_for_read</oa></addata></record>
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ispartof Journal of nuclear science and technology, 1998-09, Vol.35 (9), p.643-653
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1881-1248
language eng
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source Taylor and Francis Science and Technology Collection
subjects annular-mist flow
Applied sciences
BWR type reactors
critical heat flux
deposition
droplets
Energy
Energy. Thermal use of fuels
entrainment
Exact sciences and technology
Fission nuclear power plants
heated tube
Installations for energy generation and conversion: thermal and electrical energy
liquid film dryout
three-fluid streams
tight lattice
title Prediction of Liquid Film Dryout in Two-Phase Annular-Mist Flow in a Uniformly Heated Narrow Tube Development of Analytical Method under BWR Conditions
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