Thermal hydraulic performance analysis of the printed circuit heat exchanger using a helium test facility and CFD simulations
The thermal-hydraulic performance of the PCHE was investigated using the KAIST helium test loop. Experiments were performed in the helium laminar region with 350 < Re < 1200. The hot/cold side inlet conditions were 25–550 °C/25–100 °C over the operating pressure of 1.5–1.9 MPa, respectively. M...
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creator | Kim, In Hun No, Hee Cheon Lee, Jeong Ik Jeon, Byong Guk |
description | The thermal-hydraulic performance of the PCHE was investigated using the KAIST helium test loop. Experiments were performed in the helium laminar region with 350
<
Re
<
1200. The hot/cold side inlet conditions were 25–550
°C/25–100
°C over the operating pressure of 1.5–1.9
MPa, respectively. Mass flow rates were controlled in the range of 40–100
kg/h. Pressure drop and temperature difference were measured at the inlet and outlet of the hot and cold sides. A global Fanning factor correlation and a global Nusselt number correlation were proposed using information only at the inlet and outlet of the hot and cold sides. A three-dimensional (3-D) numerical simulation was performed using FLUENT, a commercial computational fluid dynamics (CFD) code, to compare simulation results to the KAIST helium test data and to obtain the local Nusselt number in the PCHE. CFD predictions showed good agreement with experimental data. A local pitch-averaged Nusselt number correlation was proposed using local temperature, pressure, surface heat fluxes, and properties provided by CFD simulations. The system analysis code, GAMMA, was also utilized to identify which correlation was more applicable for system analysis. It turns out that the proposed local pitch-averaged Nusselt number correlation from CFD simulations is more appropriate than the global Nusselt number correlation developed from experimental data. |
doi_str_mv | 10.1016/j.nucengdes.2009.07.005 |
format | Article |
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<
Re
<
1200. The hot/cold side inlet conditions were 25–550
°C/25–100
°C over the operating pressure of 1.5–1.9
MPa, respectively. Mass flow rates were controlled in the range of 40–100
kg/h. Pressure drop and temperature difference were measured at the inlet and outlet of the hot and cold sides. A global Fanning factor correlation and a global Nusselt number correlation were proposed using information only at the inlet and outlet of the hot and cold sides. A three-dimensional (3-D) numerical simulation was performed using FLUENT, a commercial computational fluid dynamics (CFD) code, to compare simulation results to the KAIST helium test data and to obtain the local Nusselt number in the PCHE. CFD predictions showed good agreement with experimental data. A local pitch-averaged Nusselt number correlation was proposed using local temperature, pressure, surface heat fluxes, and properties provided by CFD simulations. The system analysis code, GAMMA, was also utilized to identify which correlation was more applicable for system analysis. It turns out that the proposed local pitch-averaged Nusselt number correlation from CFD simulations is more appropriate than the global Nusselt number correlation developed from experimental data.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2009.07.005</identifier><identifier>CODEN: NEDEAU</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Fuels ; Installations for energy generation and conversion: thermal and electrical energy ; Nuclear fuels</subject><ispartof>Nuclear engineering and design, 2009-11, Vol.239 (11), p.2399-2408</ispartof><rights>2009 Elsevier B.V.</rights><rights>2009 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c376t-1ba06af71e170ff2afd99713c3bc8f5f619abb1107242f9b7739208d8e76a7613</citedby><cites>FETCH-LOGICAL-c376t-1ba06af71e170ff2afd99713c3bc8f5f619abb1107242f9b7739208d8e76a7613</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.nucengdes.2009.07.005$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3548,27922,27923,45993</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=22059560$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Kim, In Hun</creatorcontrib><creatorcontrib>No, Hee Cheon</creatorcontrib><creatorcontrib>Lee, Jeong Ik</creatorcontrib><creatorcontrib>Jeon, Byong Guk</creatorcontrib><title>Thermal hydraulic performance analysis of the printed circuit heat exchanger using a helium test facility and CFD simulations</title><title>Nuclear engineering and design</title><description>The thermal-hydraulic performance of the PCHE was investigated using the KAIST helium test loop. Experiments were performed in the helium laminar region with 350
<
Re
<
1200. The hot/cold side inlet conditions were 25–550
°C/25–100
°C over the operating pressure of 1.5–1.9
MPa, respectively. Mass flow rates were controlled in the range of 40–100
kg/h. Pressure drop and temperature difference were measured at the inlet and outlet of the hot and cold sides. A global Fanning factor correlation and a global Nusselt number correlation were proposed using information only at the inlet and outlet of the hot and cold sides. A three-dimensional (3-D) numerical simulation was performed using FLUENT, a commercial computational fluid dynamics (CFD) code, to compare simulation results to the KAIST helium test data and to obtain the local Nusselt number in the PCHE. CFD predictions showed good agreement with experimental data. A local pitch-averaged Nusselt number correlation was proposed using local temperature, pressure, surface heat fluxes, and properties provided by CFD simulations. The system analysis code, GAMMA, was also utilized to identify which correlation was more applicable for system analysis. It turns out that the proposed local pitch-averaged Nusselt number correlation from CFD simulations is more appropriate than the global Nusselt number correlation developed from experimental data.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Nuclear fuels</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2009</creationdate><recordtype>article</recordtype><recordid>eNqFkEFv1DAQhS1EJZaW34AvcEuwnU0cH6uFFqRKXIrEzZo4441XjrPYDmIP_e_1aqtemctIozfvzXyEfOSs5ox3Xw51WA2G_YipFoypmsmasfYN2fBeikq26vdbsmFMqKrdquYdeZ_SgZ1LiQ15epwwzuDpdBojrN4ZesRolzILBikE8KfkEl0szRPSY3Qh40iNi2Z1mU4ImeI_M0HYY6RrcmFPoYy9W2eaMWVqwTjv8ql4jXR395UmN68esltCuiFXFnzCDy_9mvy6-_a4-149_Lz_sbt9qEwju1zxAVgHVnLkklkrwI5KSd6YZjC9bW3HFQwD50yKrbBqkLJRgvVjj7ID2fHmmny--B7j8mctV-nZJYPeQ8BlTbopYHq5PQvlRWjiklJEq8vHM8ST5kyfceuDfsWtz7g1k7rgLpufXiIgGfA2Fn4uva4LwVrVdqzobi86LP_-dRh1Mg4L69FFNFmPi_tv1jNF8ZzO</recordid><startdate>20091101</startdate><enddate>20091101</enddate><creator>Kim, In Hun</creator><creator>No, Hee Cheon</creator><creator>Lee, Jeong Ik</creator><creator>Jeon, Byong Guk</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20091101</creationdate><title>Thermal hydraulic performance analysis of the printed circuit heat exchanger using a helium test facility and CFD simulations</title><author>Kim, In Hun ; No, Hee Cheon ; Lee, Jeong Ik ; Jeon, Byong Guk</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c376t-1ba06af71e170ff2afd99713c3bc8f5f619abb1107242f9b7739208d8e76a7613</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2009</creationdate><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Nuclear fuels</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Kim, In Hun</creatorcontrib><creatorcontrib>No, Hee Cheon</creatorcontrib><creatorcontrib>Lee, Jeong Ik</creatorcontrib><creatorcontrib>Jeon, Byong Guk</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Kim, In Hun</au><au>No, Hee Cheon</au><au>Lee, Jeong Ik</au><au>Jeon, Byong Guk</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Thermal hydraulic performance analysis of the printed circuit heat exchanger using a helium test facility and CFD simulations</atitle><jtitle>Nuclear engineering and design</jtitle><date>2009-11-01</date><risdate>2009</risdate><volume>239</volume><issue>11</issue><spage>2399</spage><epage>2408</epage><pages>2399-2408</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><coden>NEDEAU</coden><abstract>The thermal-hydraulic performance of the PCHE was investigated using the KAIST helium test loop. Experiments were performed in the helium laminar region with 350
<
Re
<
1200. The hot/cold side inlet conditions were 25–550
°C/25–100
°C over the operating pressure of 1.5–1.9
MPa, respectively. Mass flow rates were controlled in the range of 40–100
kg/h. Pressure drop and temperature difference were measured at the inlet and outlet of the hot and cold sides. A global Fanning factor correlation and a global Nusselt number correlation were proposed using information only at the inlet and outlet of the hot and cold sides. A three-dimensional (3-D) numerical simulation was performed using FLUENT, a commercial computational fluid dynamics (CFD) code, to compare simulation results to the KAIST helium test data and to obtain the local Nusselt number in the PCHE. CFD predictions showed good agreement with experimental data. A local pitch-averaged Nusselt number correlation was proposed using local temperature, pressure, surface heat fluxes, and properties provided by CFD simulations. The system analysis code, GAMMA, was also utilized to identify which correlation was more applicable for system analysis. It turns out that the proposed local pitch-averaged Nusselt number correlation from CFD simulations is more appropriate than the global Nusselt number correlation developed from experimental data.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2009.07.005</doi><tpages>10</tpages></addata></record> |
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source | ScienceDirect Journals (5 years ago - present) |
subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Installations for energy generation and conversion: thermal and electrical energy Nuclear fuels |
title | Thermal hydraulic performance analysis of the printed circuit heat exchanger using a helium test facility and CFD simulations |
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