Development of advanced CRDM without canopy seal welds
Leakage of primary coolant from the canopy seal welds of control rod drive mechanism (CRDM) for PWR has been reported not only in Japan but also all over the world since the 1970s. The canopy seal weld is a circular weld designed to retain the pressure of reactor coolant while the strength of joints...
Gespeichert in:
| Veröffentlicht in: | Nuclear engineering and design 2002-05, Vol.214 (1), p.25-34 |
|---|---|
| Hauptverfasser: | , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 34 |
|---|---|
| container_issue | 1 |
| container_start_page | 25 |
| container_title | Nuclear engineering and design |
| container_volume | 214 |
| creator | Takanabe, Kiyoshi Miyake, Takashi Nagura, Yasumi |
| description | Leakage of primary coolant from the canopy seal welds of control rod drive mechanism (CRDM) for PWR has been reported not only in Japan but also all over the world since the 1970s. The canopy seal weld is a circular weld designed to retain the pressure of reactor coolant while the strength of joints is maintained by thread. Since the coolant inside the canopy seal welds makes it easier for dissolved oxygen density to increase when a plant starts up, stress corrosion cracking (SCC) becomes a potential issue. Consequently, an advanced CRDM housing that eliminates all canopy seal welds has been studied, verified, and now applied to Vessel Head Replacement (VHR) plants in Japan. |
| doi_str_mv | 10.1016/S0029-5493(02)00011-0 |
| format | Article |
| fullrecord | <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_miscellaneous_746091758</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0029549302000110</els_id><sourcerecordid>746091758</sourcerecordid><originalsourceid>FETCH-LOGICAL-c400t-ffac87ca0d9baffd14111d056193b3ee3d4edf04429c257da540ef850defdad93</originalsourceid><addsrcrecordid>eNqFkEtLxDAUhYMoOI7-BKEbX4vqTdO0zUpkxhcogg9wFzLJDUY6bU06M8y_t50ZdKd3czffOQc-Qg4pnFOg2cULQCJingp2CskZAFAawxYZ0CJP4pyL920y-EF2yV4In9CfSAYkG-Mcy7qZYtVGtY2UmatKo4lGz-PHaOHaj3rWRlpVdbOMAqoyWmBpwj7ZsaoMeLD5Q_J2c_06uosfnm7vR1cPsU4B2thapYtcKzBioqw1NKWUGuAZFWzCEJlJ0VhI00TohOdG8RTQFhwMWqOMYENysu5tfP01w9DKqQsay1JVWM-CzNMMBM150ZHHf5JJTiljrK_ka1D7OgSPVjbeTZVfSgqy9ylXPmUvS0IiVz4ldLmjzYAKWpXWd55c-A2zjHUTPXe55rDzMnfoZdAOe6fOo26lqd0_S995T4kY</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>27113339</pqid></control><display><type>article</type><title>Development of advanced CRDM without canopy seal welds</title><source>Elsevier ScienceDirect Journals Complete</source><creator>Takanabe, Kiyoshi ; Miyake, Takashi ; Nagura, Yasumi</creator><creatorcontrib>Takanabe, Kiyoshi ; Miyake, Takashi ; Nagura, Yasumi</creatorcontrib><description>Leakage of primary coolant from the canopy seal welds of control rod drive mechanism (CRDM) for PWR has been reported not only in Japan but also all over the world since the 1970s. The canopy seal weld is a circular weld designed to retain the pressure of reactor coolant while the strength of joints is maintained by thread. Since the coolant inside the canopy seal welds makes it easier for dissolved oxygen density to increase when a plant starts up, stress corrosion cracking (SCC) becomes a potential issue. Consequently, an advanced CRDM housing that eliminates all canopy seal welds has been studied, verified, and now applied to Vessel Head Replacement (VHR) plants in Japan.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/S0029-5493(02)00011-0</identifier><identifier>CODEN: NEDEAU</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Control rods ; Coolants ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Installations for energy generation and conversion: thermal and electrical energy ; Pressurized water reactors ; Seals ; Strength of materials ; Stress corrosion cracking</subject><ispartof>Nuclear engineering and design, 2002-05, Vol.214 (1), p.25-34</ispartof><rights>2002 Elsevier Science B.V.</rights><rights>2002 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c400t-ffac87ca0d9baffd14111d056193b3ee3d4edf04429c257da540ef850defdad93</citedby><cites>FETCH-LOGICAL-c400t-ffac87ca0d9baffd14111d056193b3ee3d4edf04429c257da540ef850defdad93</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/S0029-5493(02)00011-0$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>310,311,315,781,785,790,791,3551,23935,23936,25145,27929,27930,46000</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=13637110$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Takanabe, Kiyoshi</creatorcontrib><creatorcontrib>Miyake, Takashi</creatorcontrib><creatorcontrib>Nagura, Yasumi</creatorcontrib><title>Development of advanced CRDM without canopy seal welds</title><title>Nuclear engineering and design</title><description>Leakage of primary coolant from the canopy seal welds of control rod drive mechanism (CRDM) for PWR has been reported not only in Japan but also all over the world since the 1970s. The canopy seal weld is a circular weld designed to retain the pressure of reactor coolant while the strength of joints is maintained by thread. Since the coolant inside the canopy seal welds makes it easier for dissolved oxygen density to increase when a plant starts up, stress corrosion cracking (SCC) becomes a potential issue. Consequently, an advanced CRDM housing that eliminates all canopy seal welds has been studied, verified, and now applied to Vessel Head Replacement (VHR) plants in Japan.</description><subject>Applied sciences</subject><subject>Control rods</subject><subject>Coolants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Pressurized water reactors</subject><subject>Seals</subject><subject>Strength of materials</subject><subject>Stress corrosion cracking</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2002</creationdate><recordtype>article</recordtype><recordid>eNqFkEtLxDAUhYMoOI7-BKEbX4vqTdO0zUpkxhcogg9wFzLJDUY6bU06M8y_t50ZdKd3czffOQc-Qg4pnFOg2cULQCJingp2CskZAFAawxYZ0CJP4pyL920y-EF2yV4In9CfSAYkG-Mcy7qZYtVGtY2UmatKo4lGz-PHaOHaj3rWRlpVdbOMAqoyWmBpwj7ZsaoMeLD5Q_J2c_06uosfnm7vR1cPsU4B2thapYtcKzBioqw1NKWUGuAZFWzCEJlJ0VhI00TohOdG8RTQFhwMWqOMYENysu5tfP01w9DKqQsay1JVWM-CzNMMBM150ZHHf5JJTiljrK_ka1D7OgSPVjbeTZVfSgqy9ylXPmUvS0IiVz4ldLmjzYAKWpXWd55c-A2zjHUTPXe55rDzMnfoZdAOe6fOo26lqd0_S995T4kY</recordid><startdate>20020501</startdate><enddate>20020501</enddate><creator>Takanabe, Kiyoshi</creator><creator>Miyake, Takashi</creator><creator>Nagura, Yasumi</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>7TC</scope></search><sort><creationdate>20020501</creationdate><title>Development of advanced CRDM without canopy seal welds</title><author>Takanabe, Kiyoshi ; Miyake, Takashi ; Nagura, Yasumi</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c400t-ffac87ca0d9baffd14111d056193b3ee3d4edf04429c257da540ef850defdad93</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2002</creationdate><topic>Applied sciences</topic><topic>Control rods</topic><topic>Coolants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Pressurized water reactors</topic><topic>Seals</topic><topic>Strength of materials</topic><topic>Stress corrosion cracking</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Takanabe, Kiyoshi</creatorcontrib><creatorcontrib>Miyake, Takashi</creatorcontrib><creatorcontrib>Nagura, Yasumi</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Mechanical Engineering Abstracts</collection><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Takanabe, Kiyoshi</au><au>Miyake, Takashi</au><au>Nagura, Yasumi</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Development of advanced CRDM without canopy seal welds</atitle><jtitle>Nuclear engineering and design</jtitle><date>2002-05-01</date><risdate>2002</risdate><volume>214</volume><issue>1</issue><spage>25</spage><epage>34</epage><pages>25-34</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><coden>NEDEAU</coden><abstract>Leakage of primary coolant from the canopy seal welds of control rod drive mechanism (CRDM) for PWR has been reported not only in Japan but also all over the world since the 1970s. The canopy seal weld is a circular weld designed to retain the pressure of reactor coolant while the strength of joints is maintained by thread. Since the coolant inside the canopy seal welds makes it easier for dissolved oxygen density to increase when a plant starts up, stress corrosion cracking (SCC) becomes a potential issue. Consequently, an advanced CRDM housing that eliminates all canopy seal welds has been studied, verified, and now applied to Vessel Head Replacement (VHR) plants in Japan.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/S0029-5493(02)00011-0</doi><tpages>10</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0029-5493 |
| ispartof | Nuclear engineering and design, 2002-05, Vol.214 (1), p.25-34 |
| issn | 0029-5493 1872-759X |
| language | eng |
| recordid | cdi_proquest_miscellaneous_746091758 |
| source | Elsevier ScienceDirect Journals Complete |
| subjects | Applied sciences Control rods Coolants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Installations for energy generation and conversion: thermal and electrical energy Pressurized water reactors Seals Strength of materials Stress corrosion cracking |
| title | Development of advanced CRDM without canopy seal welds |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-12T00%3A00%3A46IST&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=Development%20of%20advanced%20CRDM%20without%20canopy%20seal%20welds&rft.jtitle=Nuclear%20engineering%20and%20design&rft.au=Takanabe,%20Kiyoshi&rft.date=2002-05-01&rft.volume=214&rft.issue=1&rft.spage=25&rft.epage=34&rft.pages=25-34&rft.issn=0029-5493&rft.eissn=1872-759X&rft.coden=NEDEAU&rft_id=info:doi/10.1016/S0029-5493(02)00011-0&rft_dat=%3Cproquest_cross%3E746091758%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=27113339&rft_id=info:pmid/&rft_els_id=S0029549302000110&rfr_iscdi=true |