HETS performances in He cooled power plant divertor
In the frame of the activities aimed to evaluate the performances of a He cooled divertor in the future fusion power plant, the High Efficiency Thermal Shield (HETS) concept has been proposed. This concept relies on an abrupt change of momentum of the fluid in order to increase the turbulence in the...
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| Veröffentlicht in: | Fusion engineering and design 2005-11, Vol.75, p.481-484 |
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| container_title | Fusion engineering and design |
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| creator | Pizzuto, Aldo Karditsas, Panos J. Nardi, Claudio Papastergiou, Stamos |
| description | In the frame of the activities aimed to evaluate the performances of a He cooled divertor in the future fusion power plant, the High Efficiency Thermal Shield (HETS) concept has been proposed. This concept relies on an abrupt change of momentum of the fluid in order to increase the turbulence in the gas, and therefore the heat transfer.
The requirements for the power plant divertor are, not only to sustain the required thermal flux (10
MW/m
2), but He to have such properties as to be used directly in the energy production cycle and limit the required pumping power to no more than 10% of the divertor thermal power. Analytical studies developed by ENEA and UKAEA showed that the HETS concept can satisfy all the basic requirements.
Experimental validations are required for the pressure drop estimates in HETS. Preliminary experiments have been performed using air at room temperature and showed values of pressure drop in line with the parameters used in the calculations. Studies aimed to optimize the shape of the channel, to further reduce the pressure drop are in progress. |
| doi_str_mv | 10.1016/j.fusengdes.2005.06.008 |
| format | Article |
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The requirements for the power plant divertor are, not only to sustain the required thermal flux (10
MW/m
2), but He to have such properties as to be used directly in the energy production cycle and limit the required pumping power to no more than 10% of the divertor thermal power. Analytical studies developed by ENEA and UKAEA showed that the HETS concept can satisfy all the basic requirements.
Experimental validations are required for the pressure drop estimates in HETS. Preliminary experiments have been performed using air at room temperature and showed values of pressure drop in line with the parameters used in the calculations. Studies aimed to optimize the shape of the channel, to further reduce the pressure drop are in progress.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2005.06.008</identifier><identifier>CODEN: FEDEEE</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 ; Helium heat transfer ; High heat flux components ; High temperature brazing ; Installations for energy generation and conversion: thermal and electrical energy ; Tungsten and tungsten alloys</subject><ispartof>Fusion engineering and design, 2005-11, Vol.75, p.481-484</ispartof><rights>2005 Elsevier B.V.</rights><rights>2006 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c376t-10193b763a227276f7b10582e092c4bc2034183956ffab260aeb26b1061431713</citedby></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.fusengdes.2005.06.008$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,780,784,789,790,3550,23930,23931,25140,27924,27925,45995</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=17350328$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Pizzuto, Aldo</creatorcontrib><creatorcontrib>Karditsas, Panos J.</creatorcontrib><creatorcontrib>Nardi, Claudio</creatorcontrib><creatorcontrib>Papastergiou, Stamos</creatorcontrib><title>HETS performances in He cooled power plant divertor</title><title>Fusion engineering and design</title><description>In the frame of the activities aimed to evaluate the performances of a He cooled divertor in the future fusion power plant, the High Efficiency Thermal Shield (HETS) concept has been proposed. This concept relies on an abrupt change of momentum of the fluid in order to increase the turbulence in the gas, and therefore the heat transfer.
The requirements for the power plant divertor are, not only to sustain the required thermal flux (10
MW/m
2), but He to have such properties as to be used directly in the energy production cycle and limit the required pumping power to no more than 10% of the divertor thermal power. Analytical studies developed by ENEA and UKAEA showed that the HETS concept can satisfy all the basic requirements.
Experimental validations are required for the pressure drop estimates in HETS. Preliminary experiments have been performed using air at room temperature and showed values of pressure drop in line with the parameters used in the calculations. Studies aimed to optimize the shape of the channel, to further reduce the pressure drop are in progress.</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>Helium heat transfer</subject><subject>High heat flux components</subject><subject>High temperature brazing</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Tungsten and tungsten alloys</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2005</creationdate><recordtype>article</recordtype><recordid>eNqFkEFLwzAYhoMoOKe_wV701volaZP2OMZ0wsCD8xzS9KtkdE1Nuon_3swNPQohuTxf3vd7CLmlkFGg4mGTtbuA_XuDIWMARQYiAyjPyISWkqeSVuKcTKBikHJZiUtyFcIGgMp4JoQvF-vXZEDfOr_VvcGQ2D5ZYmKc67BJBveJPhk63Y9JY_foR-evyUWru4A3p3dK3h4X6_kyXb08Pc9nq9RwKcY0tqt4LQXXjEkmRStrCkXJMHYxeW0Y8JyWvCpE2-qaCdAY78gImnMqKZ-S--O_g3cfOwyj2tpgsItl0O2CYlUeM6CMoDyCxrsQPLZq8Har_ZeioA6S1Eb9SlIHSQqEgp_Ju1OEDkZ3rY8KbPgbl7wAzg7c7Mhh3Hdv0atgLEZdjfVoRtU4-2_WN-0efuw</recordid><startdate>20051101</startdate><enddate>20051101</enddate><creator>Pizzuto, Aldo</creator><creator>Karditsas, Panos J.</creator><creator>Nardi, Claudio</creator><creator>Papastergiou, Stamos</creator><general>Elsevier B.V</general><general>Elsevier Science</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7TB</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20051101</creationdate><title>HETS performances in He cooled power plant divertor</title><author>Pizzuto, Aldo ; Karditsas, Panos J. ; Nardi, Claudio ; Papastergiou, Stamos</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c376t-10193b763a227276f7b10582e092c4bc2034183956ffab260aeb26b1061431713</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2005</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>Helium heat transfer</topic><topic>High heat flux components</topic><topic>High temperature brazing</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Tungsten and tungsten alloys</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Pizzuto, Aldo</creatorcontrib><creatorcontrib>Karditsas, Panos J.</creatorcontrib><creatorcontrib>Nardi, Claudio</creatorcontrib><creatorcontrib>Papastergiou, Stamos</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity 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>Fusion engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Pizzuto, Aldo</au><au>Karditsas, Panos J.</au><au>Nardi, Claudio</au><au>Papastergiou, Stamos</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>HETS performances in He cooled power plant divertor</atitle><jtitle>Fusion engineering and design</jtitle><date>2005-11-01</date><risdate>2005</risdate><volume>75</volume><spage>481</spage><epage>484</epage><pages>481-484</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><coden>FEDEEE</coden><abstract>In the frame of the activities aimed to evaluate the performances of a He cooled divertor in the future fusion power plant, the High Efficiency Thermal Shield (HETS) concept has been proposed. This concept relies on an abrupt change of momentum of the fluid in order to increase the turbulence in the gas, and therefore the heat transfer.
The requirements for the power plant divertor are, not only to sustain the required thermal flux (10
MW/m
2), but He to have such properties as to be used directly in the energy production cycle and limit the required pumping power to no more than 10% of the divertor thermal power. Analytical studies developed by ENEA and UKAEA showed that the HETS concept can satisfy all the basic requirements.
Experimental validations are required for the pressure drop estimates in HETS. Preliminary experiments have been performed using air at room temperature and showed values of pressure drop in line with the parameters used in the calculations. Studies aimed to optimize the shape of the channel, to further reduce the pressure drop are in progress.</abstract><cop>Amsterdam</cop><cop>New York, NY</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2005.06.008</doi><tpages>4</tpages></addata></record> |
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| ispartof | Fusion engineering and design, 2005-11, Vol.75, p.481-484 |
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| language | eng |
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| source | Access via ScienceDirect (Elsevier) |
| subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Helium heat transfer High heat flux components High temperature brazing Installations for energy generation and conversion: thermal and electrical energy Tungsten and tungsten alloys |
| title | HETS performances in He cooled power plant divertor |
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