Measurement of flow-induced pressure variation in a scale-down SMART model
► A scale-down SMART model was constructed. ► The characteristics of the pressure distribution is experimentally estimated. ► The measured pressure is analyzed by FFT analysis. ► The characteristics of flow induced pressure in the scale-down model are estimated. A scale-down SMART reactor model was...
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Veröffentlicht in: | Nuclear engineering and design 2012-12, Vol.253, p.50-59 |
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description | ► A scale-down SMART model was constructed. ► The characteristics of the pressure distribution is experimentally estimated. ► The measured pressure is analyzed by FFT analysis. ► The characteristics of flow induced pressure in the scale-down model are estimated.
A scale-down SMART reactor model was constructed to evaluate flow-induced pressure variation under normal operating conditions. The flow rate and number of operating pumps were varied, and pressure fluctuations along the reactor internals surface of the model were measured by pressure transducers. The measured transient pressure was separated into the mean and fluctuating pressure, which was evaluated by analyzing the data of two distinct regions. Specifically, the pressure obtained at frequencies less than 10Hz was analyzed separately from those obtained at frequencies greater than 10Hz. In the present study, the mean pressure distribution was dependent on the pressure loss due to the skin friction and changes in the static pressure due to height level differences at the measuring points. The mean pressures were similar, regardless of the location of the operating pump, because the fluid was fully mixed in the upper shell. The normalized mean pressure ratio, excluding the hydrostatic pressure change, kept constant regardless of the flow rate and number of operating pumps. It was observed that the RMS of the fluctuating pressure at frequencies less than 10Hz did not depend on the measuring points for all of the surfaces of the model. And, periodic pressure fluctuation generated by the inlet region is not reachable to the fuel assembly region because of the structural arrangement of SMART. |
doi_str_mv | 10.1016/j.nucengdes.2012.08.006 |
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A scale-down SMART reactor model was constructed to evaluate flow-induced pressure variation under normal operating conditions. The flow rate and number of operating pumps were varied, and pressure fluctuations along the reactor internals surface of the model were measured by pressure transducers. The measured transient pressure was separated into the mean and fluctuating pressure, which was evaluated by analyzing the data of two distinct regions. Specifically, the pressure obtained at frequencies less than 10Hz was analyzed separately from those obtained at frequencies greater than 10Hz. In the present study, the mean pressure distribution was dependent on the pressure loss due to the skin friction and changes in the static pressure due to height level differences at the measuring points. The mean pressures were similar, regardless of the location of the operating pump, because the fluid was fully mixed in the upper shell. The normalized mean pressure ratio, excluding the hydrostatic pressure change, kept constant regardless of the flow rate and number of operating pumps. It was observed that the RMS of the fluctuating pressure at frequencies less than 10Hz did not depend on the measuring points for all of the surfaces of the model. And, periodic pressure fluctuation generated by the inlet region is not reachable to the fuel assembly region because of the structural arrangement of SMART.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2012.08.006</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 ; Flow rate ; Fluctuation ; Fuels ; Installations for energy generation and conversion: thermal and electrical energy ; Nuclear engineering ; Nuclear fuels ; Nuclear power generation ; Nuclear reactor components ; Nuclear reactors ; Pumps ; Skin friction</subject><ispartof>Nuclear engineering and design, 2012-12, Vol.253, p.50-59</ispartof><rights>2012 Elsevier B.V.</rights><rights>2014 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c378t-c9260fb5dc623e4912a14469a871ee1ee7461ece644624f1d2bae53e322c03603</citedby><cites>FETCH-LOGICAL-c378t-c9260fb5dc623e4912a14469a871ee1ee7461ece644624f1d2bae53e322c03603</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0029549312004372$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,776,780,3537,27903,27904,65309</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=26751105$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Lee, Byoung In</creatorcontrib><creatorcontrib>Kim, Kyoung Min</creatorcontrib><creatorcontrib>Lee, Dong Hwi</creatorcontrib><creatorcontrib>Cho, Hyung Hee</creatorcontrib><creatorcontrib>Jeong, Kyeong Hoon</creatorcontrib><creatorcontrib>Park, Jin Seok</creatorcontrib><title>Measurement of flow-induced pressure variation in a scale-down SMART model</title><title>Nuclear engineering and design</title><description>► A scale-down SMART model was constructed. ► The characteristics of the pressure distribution is experimentally estimated. ► The measured pressure is analyzed by FFT analysis. ► The characteristics of flow induced pressure in the scale-down model are estimated.
A scale-down SMART reactor model was constructed to evaluate flow-induced pressure variation under normal operating conditions. The flow rate and number of operating pumps were varied, and pressure fluctuations along the reactor internals surface of the model were measured by pressure transducers. The measured transient pressure was separated into the mean and fluctuating pressure, which was evaluated by analyzing the data of two distinct regions. Specifically, the pressure obtained at frequencies less than 10Hz was analyzed separately from those obtained at frequencies greater than 10Hz. In the present study, the mean pressure distribution was dependent on the pressure loss due to the skin friction and changes in the static pressure due to height level differences at the measuring points. The mean pressures were similar, regardless of the location of the operating pump, because the fluid was fully mixed in the upper shell. The normalized mean pressure ratio, excluding the hydrostatic pressure change, kept constant regardless of the flow rate and number of operating pumps. It was observed that the RMS of the fluctuating pressure at frequencies less than 10Hz did not depend on the measuring points for all of the surfaces of the model. And, periodic pressure fluctuation generated by the inlet region is not reachable to the fuel assembly region because of the structural arrangement of SMART.</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>Flow rate</subject><subject>Fluctuation</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Nuclear engineering</subject><subject>Nuclear fuels</subject><subject>Nuclear power generation</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Pumps</subject><subject>Skin friction</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2012</creationdate><recordtype>article</recordtype><recordid>eNqFkN9LwzAQx4MoOKd_g3kRfGnNjzZtH8fwJxuCTvAtZOlVMtpkJu2G_70pG756HBzcfe973Aeha0pSSqi426R20GC_aggpI5SlpEwJESdoQsuCJUVefZ6iCSGsSvKs4ufoIoQNGaNiE_SyBBUGDx3YHrsGN63bJ8bW0bLGWw9hHOKd8kb1xllsLFY4aNVCUru9xe_L2dsKd66G9hKdNaoNcHWsU_TxcL-aPyWL18fn-WyRaF6UfaIrJkizzmstGIesokzRLBOVKgsKELPIBAUNIjZZ1tCarRXkHDhjmnBB-BTdHny33n0PEHrZmaChbZUFNwRJeVZFPyF4lBYHqfYuBA-N3HrTKf8jKZEjPbmRf_TkSE-SUkZ6cfPmeESN3zZeWW3C3zoTRU4pyaNudtBB_HhnwMugDdhIz3jQvayd-ffWLyetiSM</recordid><startdate>20121201</startdate><enddate>20121201</enddate><creator>Lee, Byoung In</creator><creator>Kim, Kyoung Min</creator><creator>Lee, Dong Hwi</creator><creator>Cho, Hyung Hee</creator><creator>Jeong, Kyeong Hoon</creator><creator>Park, Jin Seok</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7SU</scope><scope>7TB</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20121201</creationdate><title>Measurement of flow-induced pressure variation in a scale-down SMART model</title><author>Lee, Byoung In ; Kim, Kyoung Min ; Lee, Dong Hwi ; Cho, Hyung Hee ; Jeong, Kyeong Hoon ; Park, Jin Seok</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c378t-c9260fb5dc623e4912a14469a871ee1ee7461ece644624f1d2bae53e322c03603</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2012</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>Flow rate</topic><topic>Fluctuation</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Nuclear engineering</topic><topic>Nuclear fuels</topic><topic>Nuclear power generation</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Pumps</topic><topic>Skin friction</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Lee, Byoung In</creatorcontrib><creatorcontrib>Kim, Kyoung Min</creatorcontrib><creatorcontrib>Lee, Dong Hwi</creatorcontrib><creatorcontrib>Cho, Hyung Hee</creatorcontrib><creatorcontrib>Jeong, Kyeong Hoon</creatorcontrib><creatorcontrib>Park, Jin Seok</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Environmental Engineering Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</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>Lee, Byoung In</au><au>Kim, Kyoung Min</au><au>Lee, Dong Hwi</au><au>Cho, Hyung Hee</au><au>Jeong, Kyeong Hoon</au><au>Park, Jin Seok</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Measurement of flow-induced pressure variation in a scale-down SMART model</atitle><jtitle>Nuclear engineering and design</jtitle><date>2012-12-01</date><risdate>2012</risdate><volume>253</volume><spage>50</spage><epage>59</epage><pages>50-59</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><coden>NEDEAU</coden><abstract>► A scale-down SMART model was constructed. ► The characteristics of the pressure distribution is experimentally estimated. ► The measured pressure is analyzed by FFT analysis. ► The characteristics of flow induced pressure in the scale-down model are estimated.
A scale-down SMART reactor model was constructed to evaluate flow-induced pressure variation under normal operating conditions. The flow rate and number of operating pumps were varied, and pressure fluctuations along the reactor internals surface of the model were measured by pressure transducers. The measured transient pressure was separated into the mean and fluctuating pressure, which was evaluated by analyzing the data of two distinct regions. Specifically, the pressure obtained at frequencies less than 10Hz was analyzed separately from those obtained at frequencies greater than 10Hz. In the present study, the mean pressure distribution was dependent on the pressure loss due to the skin friction and changes in the static pressure due to height level differences at the measuring points. The mean pressures were similar, regardless of the location of the operating pump, because the fluid was fully mixed in the upper shell. The normalized mean pressure ratio, excluding the hydrostatic pressure change, kept constant regardless of the flow rate and number of operating pumps. It was observed that the RMS of the fluctuating pressure at frequencies less than 10Hz did not depend on the measuring points for all of the surfaces of the model. And, periodic pressure fluctuation generated by the inlet region is not reachable to the fuel assembly region because of the structural arrangement of SMART.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2012.08.006</doi><tpages>10</tpages></addata></record> |
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subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Flow rate Fluctuation Fuels Installations for energy generation and conversion: thermal and electrical energy Nuclear engineering Nuclear fuels Nuclear power generation Nuclear reactor components Nuclear reactors Pumps Skin friction |
title | Measurement of flow-induced pressure variation in a scale-down SMART model |
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