Investigation of heat transfer and hydraulic resistance during the flow of water with supercritical parameters in application to reactor facilities
Together with evolutionary development of light-water vessel reactor facilities with subcritical pressure, an innovative path for the development of VVER with the coolant pressure increase above a critical value has been under study since the 1960s. Of greatest interest is the possibility of increas...
Gespeichert in:
| Veröffentlicht in: | Atomic energy (New York, N.Y.) N.Y.), 2010-11, Vol.108 (6), p.415-424 |
|---|---|
| Hauptverfasser: | , , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 424 |
|---|---|
| container_issue | 6 |
| container_start_page | 415 |
| container_title | Atomic energy (New York, N.Y.) |
| container_volume | 108 |
| creator | Silin, V. A. Semchenkov, Yu. M. Alekseev, P. N. Mitkin, V. V. |
| description | Together with evolutionary development of light-water vessel reactor facilities with subcritical pressure, an innovative path for the development of VVER with the coolant pressure increase above a critical value has been under study since the 1960s. Of greatest interest is the possibility of increasing the efficiency of a power-generating unit in a nuclear power plant from 30–35% at subcritical pressure to 44–45%, reached by the same time at heat and power plants operating at steam pressure ~24 MPa and temperature 560°C and higher. However, the problems which must be solved in this approach delayed the development of reactor facilities with supercritical pressure. One problem is developing reliable methods for calculating the temperature of fuel-element cladding and the hydraulic resistance with water flow at supercritical pressure in the core. This problem is also important because according to current assessments the materials in the core will work at the limit of their possibilities. Possible approaches to a solution of this problem are examined. |
| doi_str_mv | 10.1007/s10512-010-9310-3 |
| format | Article |
| fullrecord | <record><control><sourceid>gale_proqu</sourceid><recordid>TN_cdi_proquest_journals_807532400</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><galeid>A355939335</galeid><sourcerecordid>A355939335</sourcerecordid><originalsourceid>FETCH-LOGICAL-c418t-bf709c02ee04a8c2acf0016f192bf849dff6468b86df9e2e89491dba29c9cd223</originalsourceid><addsrcrecordid>eNp1kd9uFCEUxidGE2v1AbwjJl54MfUAM7Nw2TRWN2li4p9rcpaBXZopjMC49jl8Yc9mGk0vDAkQ-H7fgfM1zWsOFxxg875w6LlogUOrJU3ySXPG-41slYD-Ke1hkG0nevW8eVHKLQDoQauz5vc2_nSlhj3WkCJLnh0cVlYzxuJdZhhHdrgfMy5TsCy7EkrFaB0blxzintWDY35KxxN5xErEMdQDK8vsss2hBosTmzHjnaPLwkJkOM_ktdariTzR1pSZRxsmAlx52TzzOBX36mE9b75ff_h29am9-fxxe3V509qOq9ru_Aa0BeEcdKisQOsB-OC5FjuvOj16P3SD2qlh9NoJp3Sn-bhDoa22oxDyvHmz-s45_VioC-Y2LTlSSaNg00vRAZDoYhXtcXImRJ-oN5bG6O6CTdH5QOeXsu-11FL2BLx7BJCmul91j0spZvv1y2MtX7U2p1Ky82bO4Q7zveFgTrmaNVdDuZpTrkYS8_bh1ViouZ6SsqH8BYUcBpBakU6sujKfknL53-_-b_4HRh21Lg</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>807532400</pqid></control><display><type>article</type><title>Investigation of heat transfer and hydraulic resistance during the flow of water with supercritical parameters in application to reactor facilities</title><source>SpringerLink Journals - AutoHoldings</source><creator>Silin, V. A. ; Semchenkov, Yu. M. ; Alekseev, P. N. ; Mitkin, V. V.</creator><creatorcontrib>Silin, V. A. ; Semchenkov, Yu. M. ; Alekseev, P. N. ; Mitkin, V. V.</creatorcontrib><description>Together with evolutionary development of light-water vessel reactor facilities with subcritical pressure, an innovative path for the development of VVER with the coolant pressure increase above a critical value has been under study since the 1960s. Of greatest interest is the possibility of increasing the efficiency of a power-generating unit in a nuclear power plant from 30–35% at subcritical pressure to 44–45%, reached by the same time at heat and power plants operating at steam pressure ~24 MPa and temperature 560°C and higher. However, the problems which must be solved in this approach delayed the development of reactor facilities with supercritical pressure. One problem is developing reliable methods for calculating the temperature of fuel-element cladding and the hydraulic resistance with water flow at supercritical pressure in the core. This problem is also important because according to current assessments the materials in the core will work at the limit of their possibilities. Possible approaches to a solution of this problem are examined.</description><identifier>ISSN: 1063-4258</identifier><identifier>EISSN: 1573-8205</identifier><identifier>DOI: 10.1007/s10512-010-9310-3</identifier><language>eng</language><publisher>Boston: Springer US</publisher><subject>Experiments ; Hadrons ; Heat transfer ; Heavy Ions ; Hydraulic measurements ; Hydraulics ; Industrial plant emissions ; Investigations ; Nuclear Chemistry ; Nuclear Energy ; Nuclear Physics ; Nuclear power plants ; Nuclear reactors ; Physical properties ; Physics ; Physics and Astronomy ; Reactors ; Studies ; Temperature ; Water ; Water flow</subject><ispartof>Atomic energy (New York, N.Y.), 2010-11, Vol.108 (6), p.415-424</ispartof><rights>Springer Science+Business Media, Inc. 2010</rights><rights>2015 INIST-CNRS</rights><rights>COPYRIGHT 2010 Springer</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c418t-bf709c02ee04a8c2acf0016f192bf849dff6468b86df9e2e89491dba29c9cd223</citedby><cites>FETCH-LOGICAL-c418t-bf709c02ee04a8c2acf0016f192bf849dff6468b86df9e2e89491dba29c9cd223</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1007/s10512-010-9310-3$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1007/s10512-010-9310-3$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>315,781,785,27926,27927,41490,42559,51321</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=23660398$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Silin, V. A.</creatorcontrib><creatorcontrib>Semchenkov, Yu. M.</creatorcontrib><creatorcontrib>Alekseev, P. N.</creatorcontrib><creatorcontrib>Mitkin, V. V.</creatorcontrib><title>Investigation of heat transfer and hydraulic resistance during the flow of water with supercritical parameters in application to reactor facilities</title><title>Atomic energy (New York, N.Y.)</title><addtitle>At Energy</addtitle><description>Together with evolutionary development of light-water vessel reactor facilities with subcritical pressure, an innovative path for the development of VVER with the coolant pressure increase above a critical value has been under study since the 1960s. Of greatest interest is the possibility of increasing the efficiency of a power-generating unit in a nuclear power plant from 30–35% at subcritical pressure to 44–45%, reached by the same time at heat and power plants operating at steam pressure ~24 MPa and temperature 560°C and higher. However, the problems which must be solved in this approach delayed the development of reactor facilities with supercritical pressure. One problem is developing reliable methods for calculating the temperature of fuel-element cladding and the hydraulic resistance with water flow at supercritical pressure in the core. This problem is also important because according to current assessments the materials in the core will work at the limit of their possibilities. Possible approaches to a solution of this problem are examined.</description><subject>Experiments</subject><subject>Hadrons</subject><subject>Heat transfer</subject><subject>Heavy Ions</subject><subject>Hydraulic measurements</subject><subject>Hydraulics</subject><subject>Industrial plant emissions</subject><subject>Investigations</subject><subject>Nuclear Chemistry</subject><subject>Nuclear Energy</subject><subject>Nuclear Physics</subject><subject>Nuclear power plants</subject><subject>Nuclear reactors</subject><subject>Physical properties</subject><subject>Physics</subject><subject>Physics and Astronomy</subject><subject>Reactors</subject><subject>Studies</subject><subject>Temperature</subject><subject>Water</subject><subject>Water flow</subject><issn>1063-4258</issn><issn>1573-8205</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2010</creationdate><recordtype>article</recordtype><sourceid>ABUWG</sourceid><sourceid>AFKRA</sourceid><sourceid>AZQEC</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><sourceid>GNUQQ</sourceid><recordid>eNp1kd9uFCEUxidGE2v1AbwjJl54MfUAM7Nw2TRWN2li4p9rcpaBXZopjMC49jl8Yc9mGk0vDAkQ-H7fgfM1zWsOFxxg875w6LlogUOrJU3ySXPG-41slYD-Ke1hkG0nevW8eVHKLQDoQauz5vc2_nSlhj3WkCJLnh0cVlYzxuJdZhhHdrgfMy5TsCy7EkrFaB0blxzintWDY35KxxN5xErEMdQDK8vsss2hBosTmzHjnaPLwkJkOM_ktdariTzR1pSZRxsmAlx52TzzOBX36mE9b75ff_h29am9-fxxe3V509qOq9ru_Aa0BeEcdKisQOsB-OC5FjuvOj16P3SD2qlh9NoJp3Sn-bhDoa22oxDyvHmz-s45_VioC-Y2LTlSSaNg00vRAZDoYhXtcXImRJ-oN5bG6O6CTdH5QOeXsu-11FL2BLx7BJCmul91j0spZvv1y2MtX7U2p1Ky82bO4Q7zveFgTrmaNVdDuZpTrkYS8_bh1ViouZ6SsqH8BYUcBpBakU6sujKfknL53-_-b_4HRh21Lg</recordid><startdate>20101101</startdate><enddate>20101101</enddate><creator>Silin, V. A.</creator><creator>Semchenkov, Yu. M.</creator><creator>Alekseev, P. N.</creator><creator>Mitkin, V. V.</creator><general>Springer US</general><general>Springer</general><general>Springer Nature B.V</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>ISR</scope><scope>3V.</scope><scope>7SP</scope><scope>7ST</scope><scope>7TB</scope><scope>7WY</scope><scope>7WZ</scope><scope>7XB</scope><scope>87Z</scope><scope>88I</scope><scope>8FD</scope><scope>8FE</scope><scope>8FG</scope><scope>8FK</scope><scope>8FL</scope><scope>ABJCF</scope><scope>ABUWG</scope><scope>AFKRA</scope><scope>ARAPS</scope><scope>AZQEC</scope><scope>BENPR</scope><scope>BEZIV</scope><scope>BGLVJ</scope><scope>BHPHI</scope><scope>BKSAR</scope><scope>C1K</scope><scope>CCPQU</scope><scope>DWQXO</scope><scope>FR3</scope><scope>FRNLG</scope><scope>F~G</scope><scope>GNUQQ</scope><scope>HCIFZ</scope><scope>K60</scope><scope>K6~</scope><scope>KR7</scope><scope>L.-</scope><scope>L6V</scope><scope>L7M</scope><scope>M0C</scope><scope>M2P</scope><scope>M7S</scope><scope>P5Z</scope><scope>P62</scope><scope>PCBAR</scope><scope>PQBIZ</scope><scope>PQBZA</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>PTHSS</scope><scope>PYYUZ</scope><scope>Q9U</scope><scope>SOI</scope></search><sort><creationdate>20101101</creationdate><title>Investigation of heat transfer and hydraulic resistance during the flow of water with supercritical parameters in application to reactor facilities</title><author>Silin, V. A. ; Semchenkov, Yu. M. ; Alekseev, P. N. ; Mitkin, V. V.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c418t-bf709c02ee04a8c2acf0016f192bf849dff6468b86df9e2e89491dba29c9cd223</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2010</creationdate><topic>Experiments</topic><topic>Hadrons</topic><topic>Heat transfer</topic><topic>Heavy Ions</topic><topic>Hydraulic measurements</topic><topic>Hydraulics</topic><topic>Industrial plant emissions</topic><topic>Investigations</topic><topic>Nuclear Chemistry</topic><topic>Nuclear Energy</topic><topic>Nuclear Physics</topic><topic>Nuclear power plants</topic><topic>Nuclear reactors</topic><topic>Physical properties</topic><topic>Physics</topic><topic>Physics and Astronomy</topic><topic>Reactors</topic><topic>Studies</topic><topic>Temperature</topic><topic>Water</topic><topic>Water flow</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Silin, V. A.</creatorcontrib><creatorcontrib>Semchenkov, Yu. M.</creatorcontrib><creatorcontrib>Alekseev, P. N.</creatorcontrib><creatorcontrib>Mitkin, V. V.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Gale In Context: Science</collection><collection>ProQuest Central (Corporate)</collection><collection>Electronics & Communications Abstracts</collection><collection>Environment Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Access via ABI/INFORM (ProQuest)</collection><collection>ABI/INFORM Global (PDF only)</collection><collection>ProQuest Central (purchase pre-March 2016)</collection><collection>ABI/INFORM Global (Alumni Edition)</collection><collection>Science Database (Alumni Edition)</collection><collection>Technology Research Database</collection><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>ProQuest Central (Alumni) (purchase pre-March 2016)</collection><collection>ABI/INFORM Collection (Alumni Edition)</collection><collection>Materials Science & Engineering Collection</collection><collection>ProQuest Central (Alumni Edition)</collection><collection>ProQuest Central UK/Ireland</collection><collection>Advanced Technologies & Aerospace Collection</collection><collection>ProQuest Central Essentials</collection><collection>ProQuest Central</collection><collection>Business Premium Collection</collection><collection>Technology Collection</collection><collection>Natural Science Collection</collection><collection>Earth, Atmospheric & Aquatic Science Collection</collection><collection>Environmental Sciences and Pollution Management</collection><collection>ProQuest One Community College</collection><collection>ProQuest Central Korea</collection><collection>Engineering Research Database</collection><collection>Business Premium Collection (Alumni)</collection><collection>ABI/INFORM Global (Corporate)</collection><collection>ProQuest Central Student</collection><collection>SciTech Premium Collection</collection><collection>ProQuest Business Collection (Alumni Edition)</collection><collection>ProQuest Business Collection</collection><collection>Civil Engineering Abstracts</collection><collection>ABI/INFORM Professional Advanced</collection><collection>ProQuest Engineering Collection</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>ABI/INFORM Global</collection><collection>Science Database</collection><collection>Engineering Database</collection><collection>Advanced Technologies & Aerospace Database</collection><collection>ProQuest Advanced Technologies & Aerospace Collection</collection><collection>Earth, Atmospheric & Aquatic Science Database</collection><collection>ProQuest One Business</collection><collection>ProQuest One Business (Alumni)</collection><collection>ProQuest One Academic Eastern Edition (DO NOT USE)</collection><collection>ProQuest One Academic</collection><collection>ProQuest One Academic UKI Edition</collection><collection>Engineering Collection</collection><collection>ABI/INFORM Collection China</collection><collection>ProQuest Central Basic</collection><collection>Environment Abstracts</collection><jtitle>Atomic energy (New York, N.Y.)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Silin, V. A.</au><au>Semchenkov, Yu. M.</au><au>Alekseev, P. N.</au><au>Mitkin, V. V.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Investigation of heat transfer and hydraulic resistance during the flow of water with supercritical parameters in application to reactor facilities</atitle><jtitle>Atomic energy (New York, N.Y.)</jtitle><stitle>At Energy</stitle><date>2010-11-01</date><risdate>2010</risdate><volume>108</volume><issue>6</issue><spage>415</spage><epage>424</epage><pages>415-424</pages><issn>1063-4258</issn><eissn>1573-8205</eissn><abstract>Together with evolutionary development of light-water vessel reactor facilities with subcritical pressure, an innovative path for the development of VVER with the coolant pressure increase above a critical value has been under study since the 1960s. Of greatest interest is the possibility of increasing the efficiency of a power-generating unit in a nuclear power plant from 30–35% at subcritical pressure to 44–45%, reached by the same time at heat and power plants operating at steam pressure ~24 MPa and temperature 560°C and higher. However, the problems which must be solved in this approach delayed the development of reactor facilities with supercritical pressure. One problem is developing reliable methods for calculating the temperature of fuel-element cladding and the hydraulic resistance with water flow at supercritical pressure in the core. This problem is also important because according to current assessments the materials in the core will work at the limit of their possibilities. Possible approaches to a solution of this problem are examined.</abstract><cop>Boston</cop><pub>Springer US</pub><doi>10.1007/s10512-010-9310-3</doi><tpages>10</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 1063-4258 |
| ispartof | Atomic energy (New York, N.Y.), 2010-11, Vol.108 (6), p.415-424 |
| issn | 1063-4258 1573-8205 |
| language | eng |
| recordid | cdi_proquest_journals_807532400 |
| source | SpringerLink Journals - AutoHoldings |
| subjects | Experiments Hadrons Heat transfer Heavy Ions Hydraulic measurements Hydraulics Industrial plant emissions Investigations Nuclear Chemistry Nuclear Energy Nuclear Physics Nuclear power plants Nuclear reactors Physical properties Physics Physics and Astronomy Reactors Studies Temperature Water Water flow |
| title | Investigation of heat transfer and hydraulic resistance during the flow of water with supercritical parameters in application to reactor facilities |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-18T09%3A53%3A47IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-gale_proqu&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Investigation%20of%20heat%20transfer%20and%20hydraulic%20resistance%20during%20the%20flow%20of%20water%20with%20supercritical%20parameters%20in%20application%20to%20reactor%20facilities&rft.jtitle=Atomic%20energy%20(New%20York,%20N.Y.)&rft.au=Silin,%20V.%20A.&rft.date=2010-11-01&rft.volume=108&rft.issue=6&rft.spage=415&rft.epage=424&rft.pages=415-424&rft.issn=1063-4258&rft.eissn=1573-8205&rft_id=info:doi/10.1007/s10512-010-9310-3&rft_dat=%3Cgale_proqu%3EA355939335%3C/gale_proqu%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=807532400&rft_id=info:pmid/&rft_galeid=A355939335&rfr_iscdi=true |