Remote field eddy current testing for steam generator inspection of fast reactor

► We confirmed defect detection performances of remote field eddy current testing. ► It is difficult to inspect outer surface of double wall tube steam generator. ► We used coils with flux guide made of iron–nickel alloy for high sensitivity. ► Output voltage of detector coil increased more than 100...

Ausführliche Beschreibung

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:Nuclear engineering and design 2011-12, Vol.241 (12), p.4643-4648
Hauptverfasser: Kobayashi, Noriyasu, Ueno, Souichi, Nagai, Satoshi, Ochiai, Makoto, Jimbo, Noboru
Format: Artikel
Sprache:eng
Schlagworte:
Online-Zugang:Volltext
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
container_end_page 4648
container_issue 12
container_start_page 4643
container_title Nuclear engineering and design
container_volume 241
creator Kobayashi, Noriyasu
Ueno, Souichi
Nagai, Satoshi
Ochiai, Makoto
Jimbo, Noboru
description ► We confirmed defect detection performances of remote field eddy current testing. ► It is difficult to inspect outer surface of double wall tube steam generator. ► We used coils with flux guide made of iron–nickel alloy for high sensitivity. ► Output voltage of detector coil increased more than 100 times. ► We were able to detect small hole defect of 1mm in diameter on outer surface. We confirmed the defect detection performances of the remote field eddy current testing (RFECT) in order to inspect the helical-coil-type double wall tube steam generator (DWTSG) with the wire mesh layer for the new small fast reactor 4S (Super-Safe, Small and Simple). As the high sensitivity techniques, we tried to increase the direct magnetic field intensity in the vicinity of the inner wall of the tube and decrease the direct magnetic field around the central axis of the tube using the exciter coil with the flux guide made of the iron–nickel alloy. We adopted the horizontal type multiple detector coils with the flux guides arrayed circumferentially to enhance the sensitivity of the radial component. According to the experimental results, the output voltage of the detector coil in the region of indirect magnetic field increased more than 100 times by the application of the exciter and detector coils with the flux guides. Finally, we were able to detect the small hole defect of 1 mm in diameter and 20% of the outer tube thickness in depth over the wire mesh layer by the adoption of the exciter coil and horizontal type multiple detector coils with the flux guides. We also confirmed that the RFECT probe is useful for detecting thinning defects. These experimental results indicated that there is the possibility that we can inspect the double wall tube with the wire mesh layer using the RFECT.
doi_str_mv 10.1016/j.nucengdes.2011.03.054
format Article
fullrecord <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_miscellaneous_1671452742</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0029549311003232</els_id><sourcerecordid>1671452742</sourcerecordid><originalsourceid>FETCH-LOGICAL-c378t-486f3ab8bf9fda19afd4e70c75b3f305f2102999cd7e4b302c66c4816c5a8b3d3</originalsourceid><addsrcrecordid>eNqFkEtLAzEQx4MoWKufwVwEL7vmsbvZPZbiCwqKKHgL2WRSUrbZmqRCv70pLb06MAzD_Of1Q-iWkpIS2jysSr_V4JcGYskIpSXhJamrMzShrWCFqLvvczQhhHVFXXX8El3FuCJ769gEvX_AekyArYPBYDBmh_U2BPAJJ4jJ-SW2Y8AxgVrjJXgIKuXc-bgBndzo8WixVTHhAErn0jW6sGqIcHOMU_T19Pg5fykWb8-v89mi0Fy0qajaxnLVt73trFG0U9ZUIIgWdc8tJ7VlNF_cddoIqHpOmG4aXbW00bVqe274FN0f5m7C-LPNp8q1ixqGQXkYt1HSRtCqZqJiWSoOUh3GGANYuQlurcJOUiL3DOVKnhjKPUNJuMwMc-fdcYmKWg02KK9dPLWzmtPsJOtmBx3kj38dBBm1A6_BuJAxSTO6f3f9Abk5jPQ</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>1671452742</pqid></control><display><type>article</type><title>Remote field eddy current testing for steam generator inspection of fast reactor</title><source>Elsevier ScienceDirect Journals</source><creator>Kobayashi, Noriyasu ; Ueno, Souichi ; Nagai, Satoshi ; Ochiai, Makoto ; Jimbo, Noboru</creator><creatorcontrib>Kobayashi, Noriyasu ; Ueno, Souichi ; Nagai, Satoshi ; Ochiai, Makoto ; Jimbo, Noboru</creatorcontrib><description>► We confirmed defect detection performances of remote field eddy current testing. ► It is difficult to inspect outer surface of double wall tube steam generator. ► We used coils with flux guide made of iron–nickel alloy for high sensitivity. ► Output voltage of detector coil increased more than 100 times. ► We were able to detect small hole defect of 1mm in diameter on outer surface. We confirmed the defect detection performances of the remote field eddy current testing (RFECT) in order to inspect the helical-coil-type double wall tube steam generator (DWTSG) with the wire mesh layer for the new small fast reactor 4S (Super-Safe, Small and Simple). As the high sensitivity techniques, we tried to increase the direct magnetic field intensity in the vicinity of the inner wall of the tube and decrease the direct magnetic field around the central axis of the tube using the exciter coil with the flux guide made of the iron–nickel alloy. We adopted the horizontal type multiple detector coils with the flux guides arrayed circumferentially to enhance the sensitivity of the radial component. According to the experimental results, the output voltage of the detector coil in the region of indirect magnetic field increased more than 100 times by the application of the exciter and detector coils with the flux guides. Finally, we were able to detect the small hole defect of 1 mm in diameter and 20% of the outer tube thickness in depth over the wire mesh layer by the adoption of the exciter coil and horizontal type multiple detector coils with the flux guides. We also confirmed that the RFECT probe is useful for detecting thinning defects. These experimental results indicated that there is the possibility that we can inspect the double wall tube with the wire mesh layer using the RFECT.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2011.03.054</identifier><identifier>CODEN: NEDEAU</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Coiling ; Controled nuclear fusion plants ; Detectors ; Double wall tube ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fast reactor ; Fission nuclear power plants ; Flux ; Fuels ; Installations for energy generation and conversion: thermal and electrical energy ; Magnetic fields ; Nuclear fuels ; Nuclear reactor components ; Nuclear reactors ; Remote field eddy current testing ; Steam generator ; Tubes ; Walls ; Wire mesh layer</subject><ispartof>Nuclear engineering and design, 2011-12, Vol.241 (12), p.4643-4648</ispartof><rights>2011 Elsevier B.V.</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c378t-486f3ab8bf9fda19afd4e70c75b3f305f2102999cd7e4b302c66c4816c5a8b3d3</citedby><cites>FETCH-LOGICAL-c378t-486f3ab8bf9fda19afd4e70c75b3f305f2102999cd7e4b302c66c4816c5a8b3d3</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.2011.03.054$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,777,781,786,787,3537,23911,23912,25121,27905,27906,45976</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&amp;idt=25312530$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Kobayashi, Noriyasu</creatorcontrib><creatorcontrib>Ueno, Souichi</creatorcontrib><creatorcontrib>Nagai, Satoshi</creatorcontrib><creatorcontrib>Ochiai, Makoto</creatorcontrib><creatorcontrib>Jimbo, Noboru</creatorcontrib><title>Remote field eddy current testing for steam generator inspection of fast reactor</title><title>Nuclear engineering and design</title><description>► We confirmed defect detection performances of remote field eddy current testing. ► It is difficult to inspect outer surface of double wall tube steam generator. ► We used coils with flux guide made of iron–nickel alloy for high sensitivity. ► Output voltage of detector coil increased more than 100 times. ► We were able to detect small hole defect of 1mm in diameter on outer surface. We confirmed the defect detection performances of the remote field eddy current testing (RFECT) in order to inspect the helical-coil-type double wall tube steam generator (DWTSG) with the wire mesh layer for the new small fast reactor 4S (Super-Safe, Small and Simple). As the high sensitivity techniques, we tried to increase the direct magnetic field intensity in the vicinity of the inner wall of the tube and decrease the direct magnetic field around the central axis of the tube using the exciter coil with the flux guide made of the iron–nickel alloy. We adopted the horizontal type multiple detector coils with the flux guides arrayed circumferentially to enhance the sensitivity of the radial component. According to the experimental results, the output voltage of the detector coil in the region of indirect magnetic field increased more than 100 times by the application of the exciter and detector coils with the flux guides. Finally, we were able to detect the small hole defect of 1 mm in diameter and 20% of the outer tube thickness in depth over the wire mesh layer by the adoption of the exciter coil and horizontal type multiple detector coils with the flux guides. We also confirmed that the RFECT probe is useful for detecting thinning defects. These experimental results indicated that there is the possibility that we can inspect the double wall tube with the wire mesh layer using the RFECT.</description><subject>Applied sciences</subject><subject>Coiling</subject><subject>Controled nuclear fusion plants</subject><subject>Detectors</subject><subject>Double wall tube</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fast reactor</subject><subject>Fission nuclear power plants</subject><subject>Flux</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Magnetic fields</subject><subject>Nuclear fuels</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Remote field eddy current testing</subject><subject>Steam generator</subject><subject>Tubes</subject><subject>Walls</subject><subject>Wire mesh layer</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2011</creationdate><recordtype>article</recordtype><recordid>eNqFkEtLAzEQx4MoWKufwVwEL7vmsbvZPZbiCwqKKHgL2WRSUrbZmqRCv70pLb06MAzD_Of1Q-iWkpIS2jysSr_V4JcGYskIpSXhJamrMzShrWCFqLvvczQhhHVFXXX8El3FuCJ769gEvX_AekyArYPBYDBmh_U2BPAJJ4jJ-SW2Y8AxgVrjJXgIKuXc-bgBndzo8WixVTHhAErn0jW6sGqIcHOMU_T19Pg5fykWb8-v89mi0Fy0qajaxnLVt73trFG0U9ZUIIgWdc8tJ7VlNF_cddoIqHpOmG4aXbW00bVqe274FN0f5m7C-LPNp8q1ixqGQXkYt1HSRtCqZqJiWSoOUh3GGANYuQlurcJOUiL3DOVKnhjKPUNJuMwMc-fdcYmKWg02KK9dPLWzmtPsJOtmBx3kj38dBBm1A6_BuJAxSTO6f3f9Abk5jPQ</recordid><startdate>20111201</startdate><enddate>20111201</enddate><creator>Kobayashi, Noriyasu</creator><creator>Ueno, Souichi</creator><creator>Nagai, Satoshi</creator><creator>Ochiai, Makoto</creator><creator>Jimbo, Noboru</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>20111201</creationdate><title>Remote field eddy current testing for steam generator inspection of fast reactor</title><author>Kobayashi, Noriyasu ; Ueno, Souichi ; Nagai, Satoshi ; Ochiai, Makoto ; Jimbo, Noboru</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c378t-486f3ab8bf9fda19afd4e70c75b3f305f2102999cd7e4b302c66c4816c5a8b3d3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2011</creationdate><topic>Applied sciences</topic><topic>Coiling</topic><topic>Controled nuclear fusion plants</topic><topic>Detectors</topic><topic>Double wall tube</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fast reactor</topic><topic>Fission nuclear power plants</topic><topic>Flux</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Magnetic fields</topic><topic>Nuclear fuels</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Remote field eddy current testing</topic><topic>Steam generator</topic><topic>Tubes</topic><topic>Walls</topic><topic>Wire mesh layer</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Kobayashi, Noriyasu</creatorcontrib><creatorcontrib>Ueno, Souichi</creatorcontrib><creatorcontrib>Nagai, Satoshi</creatorcontrib><creatorcontrib>Ochiai, Makoto</creatorcontrib><creatorcontrib>Jimbo, Noboru</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics &amp; Communications Abstracts</collection><collection>Environmental Engineering Abstracts</collection><collection>Mechanical &amp; 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>Kobayashi, Noriyasu</au><au>Ueno, Souichi</au><au>Nagai, Satoshi</au><au>Ochiai, Makoto</au><au>Jimbo, Noboru</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Remote field eddy current testing for steam generator inspection of fast reactor</atitle><jtitle>Nuclear engineering and design</jtitle><date>2011-12-01</date><risdate>2011</risdate><volume>241</volume><issue>12</issue><spage>4643</spage><epage>4648</epage><pages>4643-4648</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><coden>NEDEAU</coden><abstract>► We confirmed defect detection performances of remote field eddy current testing. ► It is difficult to inspect outer surface of double wall tube steam generator. ► We used coils with flux guide made of iron–nickel alloy for high sensitivity. ► Output voltage of detector coil increased more than 100 times. ► We were able to detect small hole defect of 1mm in diameter on outer surface. We confirmed the defect detection performances of the remote field eddy current testing (RFECT) in order to inspect the helical-coil-type double wall tube steam generator (DWTSG) with the wire mesh layer for the new small fast reactor 4S (Super-Safe, Small and Simple). As the high sensitivity techniques, we tried to increase the direct magnetic field intensity in the vicinity of the inner wall of the tube and decrease the direct magnetic field around the central axis of the tube using the exciter coil with the flux guide made of the iron–nickel alloy. We adopted the horizontal type multiple detector coils with the flux guides arrayed circumferentially to enhance the sensitivity of the radial component. According to the experimental results, the output voltage of the detector coil in the region of indirect magnetic field increased more than 100 times by the application of the exciter and detector coils with the flux guides. Finally, we were able to detect the small hole defect of 1 mm in diameter and 20% of the outer tube thickness in depth over the wire mesh layer by the adoption of the exciter coil and horizontal type multiple detector coils with the flux guides. We also confirmed that the RFECT probe is useful for detecting thinning defects. These experimental results indicated that there is the possibility that we can inspect the double wall tube with the wire mesh layer using the RFECT.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2011.03.054</doi><tpages>6</tpages></addata></record>
fulltext fulltext
identifier ISSN: 0029-5493
ispartof Nuclear engineering and design, 2011-12, Vol.241 (12), p.4643-4648
issn 0029-5493
1872-759X
language eng
recordid cdi_proquest_miscellaneous_1671452742
source Elsevier ScienceDirect Journals
subjects Applied sciences
Coiling
Controled nuclear fusion plants
Detectors
Double wall tube
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fast reactor
Fission nuclear power plants
Flux
Fuels
Installations for energy generation and conversion: thermal and electrical energy
Magnetic fields
Nuclear fuels
Nuclear reactor components
Nuclear reactors
Remote field eddy current testing
Steam generator
Tubes
Walls
Wire mesh layer
title Remote field eddy current testing for steam generator inspection of fast reactor
url https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-17T21%3A11%3A40IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_cross&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Remote%20field%20eddy%20current%20testing%20for%20steam%20generator%20inspection%20of%20fast%20reactor&rft.jtitle=Nuclear%20engineering%20and%20design&rft.au=Kobayashi,%20Noriyasu&rft.date=2011-12-01&rft.volume=241&rft.issue=12&rft.spage=4643&rft.epage=4648&rft.pages=4643-4648&rft.issn=0029-5493&rft.eissn=1872-759X&rft.coden=NEDEAU&rft_id=info:doi/10.1016/j.nucengdes.2011.03.054&rft_dat=%3Cproquest_cross%3E1671452742%3C/proquest_cross%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=1671452742&rft_id=info:pmid/&rft_els_id=S0029549311003232&rfr_iscdi=true