Integrity Evaluation System of CANDU Reactor Pressure Tube
The pressure tube is a major component of the CANDU reactor, which supports nuclear fuel bundle. In order to complete the integrity evaluation of pressure tube, expert knowledge, iterative calculation procedures and a lot of input data are required. More over, results of integrity assessment may be...
Gespeichert in:
| Veröffentlicht in: | Journal of mechanical science and technology 2003-07, Vol.17 (7), p.947-957 |
|---|---|
| Hauptverfasser: | , , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 957 |
|---|---|
| container_issue | 7 |
| container_start_page | 947 |
| container_title | Journal of mechanical science and technology |
| container_volume | 17 |
| creator | KIM, Young-Jin KWAK, Sang-Log LEE, Joon-Seong PARK, Youn-Won |
| description | The pressure tube is a major component of the CANDU reactor, which supports nuclear fuel bundle. In order to complete the integrity evaluation of pressure tube, expert knowledge, iterative calculation procedures and a lot of input data are required. More over, results of integrity assessment may be different according to the evaluation method. For this reason, an integrity evaluation system, which provides efficient way of evaluation with the help of attached database, was developed. The present system was built on the basis of 3D FEM results, ASME Sec. XI, and Fitness For Service Guidelines for CANDU pressure tubes issued by the AECL (Atomic Energy Canada Limited). The present system also covers the delayed hydride cracking and the blister evaluation, which are the characteristics of pressure tube integrity evaluation. In order to verify the present system, several case studies have been performed and the results were compared with those from AECL. A good agreement was observed between those two results. |
| doi_str_mv | 10.1007/BF02982979 |
| format | Article |
| fullrecord | <record><control><sourceid>nurimedia_proqu</sourceid><recordid>TN_cdi_proquest_miscellaneous_1266752616</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><nurid>NODE00531661</nurid><sourcerecordid>NODE00531661</sourcerecordid><originalsourceid>FETCH-LOGICAL-c380t-ce082e9170528572e0471b29adab3f135d91386ddce8b96a2818bc8ad5556ca93</originalsourceid><addsrcrecordid>eNp90EtLw0AQB_BFFKzVi58gIIII0X1kX95qH1oorWgL3sJmM5GUNKm7idBvb0qLFQ-eZmB-Mwx_hC4JviMYy_vHEaZaUS31EeoQLUXIFI2O214yFUY6ej9FZ94vMRY0IqSDHsZlDR8urzfB8MsUjanzqgzeNr6GVVBlQb83HSyCVzC2rlzw4sD7xkEwbxI4RyeZKTxc7GsXLUbDef85nMyexv3eJLRM4Tq0gBUFTSTmVHFJAUeSJFSb1CQsI4ynmjAl0tSCSrQwVBGVWGVSzrmwRrMuutndXbvqswFfx6vcWygKU0LV-JhQISSngoiWXv2hy6pxZftdTKWSNJIU4_8UwbTNkUm9Vbc7ZV3lvYMsXrt8ZdymRfE27PgQdouv9yeNt6bInClt7g8bkeaS6V-ubNoRpLn5MdPZYIgxZ0QIwr4Bkq-GvA</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>1021003790</pqid></control><display><type>article</type><title>Integrity Evaluation System of CANDU Reactor Pressure Tube</title><source>SpringerLink Journals - AutoHoldings</source><creator>KIM, Young-Jin ; KWAK, Sang-Log ; LEE, Joon-Seong ; PARK, Youn-Won</creator><creatorcontrib>KIM, Young-Jin ; KWAK, Sang-Log ; LEE, Joon-Seong ; PARK, Youn-Won</creatorcontrib><description>The pressure tube is a major component of the CANDU reactor, which supports nuclear fuel bundle. In order to complete the integrity evaluation of pressure tube, expert knowledge, iterative calculation procedures and a lot of input data are required. More over, results of integrity assessment may be different according to the evaluation method. For this reason, an integrity evaluation system, which provides efficient way of evaluation with the help of attached database, was developed. The present system was built on the basis of 3D FEM results, ASME Sec. XI, and Fitness For Service Guidelines for CANDU pressure tubes issued by the AECL (Atomic Energy Canada Limited). The present system also covers the delayed hydride cracking and the blister evaluation, which are the characteristics of pressure tube integrity evaluation. In order to verify the present system, several case studies have been performed and the results were compared with those from AECL. A good agreement was observed between those two results.</description><identifier>ISSN: 1738-494X</identifier><identifier>ISSN: 1226-4865</identifier><identifier>EISSN: 1976-3824</identifier><identifier>DOI: 10.1007/BF02982979</identifier><language>eng</language><publisher>Seoul: 대한기계학회</publisher><subject>Applied sciences ; Blistering ; Candu ; Energy ; Energy. Thermal use of fuels ; Evaluation ; Exact sciences and technology ; Finite element method ; Fission nuclear power plants ; Fracture mechanics (crack, fatigue, damage...) ; Fracture mechanics, fatigue and cracks ; Fundamental areas of phenomenology (including applications) ; Heavy water reactors ; Installations for energy generation and conversion: thermal and electrical energy ; Integrity ; Mathematical models ; Mechanical engineering. Machine design ; Nuclear energy ; Nuclear fuels ; Nuclear power generation ; Nuclear reactor components ; Nuclear reactors ; Physics ; Solid mechanics ; Steel design ; Steel tanks and pressure vessels; boiler manufacturing ; Structural and continuum mechanics ; Studies ; Tubes</subject><ispartof>Journal of mechanical science and technology, 2003-07, Vol.17 (7), p.947-957</ispartof><rights>2003 INIST-CNRS</rights><rights>The Korean Society of Mechanical Engineers (KSME) 2003</rights><rights>The Korean Society of Mechanical Engineers (KSME) 2003.</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c380t-ce082e9170528572e0471b29adab3f135d91386ddce8b96a2818bc8ad5556ca93</citedby><cites>FETCH-LOGICAL-c380t-ce082e9170528572e0471b29adab3f135d91386ddce8b96a2818bc8ad5556ca93</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>315,781,785,27926,27927</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=14957399$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>KIM, Young-Jin</creatorcontrib><creatorcontrib>KWAK, Sang-Log</creatorcontrib><creatorcontrib>LEE, Joon-Seong</creatorcontrib><creatorcontrib>PARK, Youn-Won</creatorcontrib><title>Integrity Evaluation System of CANDU Reactor Pressure Tube</title><title>Journal of mechanical science and technology</title><description>The pressure tube is a major component of the CANDU reactor, which supports nuclear fuel bundle. In order to complete the integrity evaluation of pressure tube, expert knowledge, iterative calculation procedures and a lot of input data are required. More over, results of integrity assessment may be different according to the evaluation method. For this reason, an integrity evaluation system, which provides efficient way of evaluation with the help of attached database, was developed. The present system was built on the basis of 3D FEM results, ASME Sec. XI, and Fitness For Service Guidelines for CANDU pressure tubes issued by the AECL (Atomic Energy Canada Limited). The present system also covers the delayed hydride cracking and the blister evaluation, which are the characteristics of pressure tube integrity evaluation. In order to verify the present system, several case studies have been performed and the results were compared with those from AECL. A good agreement was observed between those two results.</description><subject>Applied sciences</subject><subject>Blistering</subject><subject>Candu</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Evaluation</subject><subject>Exact sciences and technology</subject><subject>Finite element method</subject><subject>Fission nuclear power plants</subject><subject>Fracture mechanics (crack, fatigue, damage...)</subject><subject>Fracture mechanics, fatigue and cracks</subject><subject>Fundamental areas of phenomenology (including applications)</subject><subject>Heavy water reactors</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Integrity</subject><subject>Mathematical models</subject><subject>Mechanical engineering. Machine design</subject><subject>Nuclear energy</subject><subject>Nuclear fuels</subject><subject>Nuclear power generation</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Physics</subject><subject>Solid mechanics</subject><subject>Steel design</subject><subject>Steel tanks and pressure vessels; boiler manufacturing</subject><subject>Structural and continuum mechanics</subject><subject>Studies</subject><subject>Tubes</subject><issn>1738-494X</issn><issn>1226-4865</issn><issn>1976-3824</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2003</creationdate><recordtype>article</recordtype><sourceid>AFKRA</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><recordid>eNp90EtLw0AQB_BFFKzVi58gIIII0X1kX95qH1oorWgL3sJmM5GUNKm7idBvb0qLFQ-eZmB-Mwx_hC4JviMYy_vHEaZaUS31EeoQLUXIFI2O214yFUY6ej9FZ94vMRY0IqSDHsZlDR8urzfB8MsUjanzqgzeNr6GVVBlQb83HSyCVzC2rlzw4sD7xkEwbxI4RyeZKTxc7GsXLUbDef85nMyexv3eJLRM4Tq0gBUFTSTmVHFJAUeSJFSb1CQsI4ynmjAl0tSCSrQwVBGVWGVSzrmwRrMuutndXbvqswFfx6vcWygKU0LV-JhQISSngoiWXv2hy6pxZftdTKWSNJIU4_8UwbTNkUm9Vbc7ZV3lvYMsXrt8ZdymRfE27PgQdouv9yeNt6bInClt7g8bkeaS6V-ubNoRpLn5MdPZYIgxZ0QIwr4Bkq-GvA</recordid><startdate>20030701</startdate><enddate>20030701</enddate><creator>KIM, Young-Jin</creator><creator>KWAK, Sang-Log</creator><creator>LEE, Joon-Seong</creator><creator>PARK, Youn-Won</creator><general>대한기계학회</general><general>Korean Society of Mechanical Engineers</general><general>Springer Nature B.V</general><scope>DBRKI</scope><scope>TDB</scope><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>8FE</scope><scope>8FG</scope><scope>ABJCF</scope><scope>AFKRA</scope><scope>BENPR</scope><scope>BGLVJ</scope><scope>CCPQU</scope><scope>DWQXO</scope><scope>FR3</scope><scope>HCIFZ</scope><scope>L6V</scope><scope>M7S</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>PRINS</scope><scope>PTHSS</scope><scope>S0W</scope></search><sort><creationdate>20030701</creationdate><title>Integrity Evaluation System of CANDU Reactor Pressure Tube</title><author>KIM, Young-Jin ; KWAK, Sang-Log ; LEE, Joon-Seong ; PARK, Youn-Won</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c380t-ce082e9170528572e0471b29adab3f135d91386ddce8b96a2818bc8ad5556ca93</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2003</creationdate><topic>Applied sciences</topic><topic>Blistering</topic><topic>Candu</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Evaluation</topic><topic>Exact sciences and technology</topic><topic>Finite element method</topic><topic>Fission nuclear power plants</topic><topic>Fracture mechanics (crack, fatigue, damage...)</topic><topic>Fracture mechanics, fatigue and cracks</topic><topic>Fundamental areas of phenomenology (including applications)</topic><topic>Heavy water reactors</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Integrity</topic><topic>Mathematical models</topic><topic>Mechanical engineering. Machine design</topic><topic>Nuclear energy</topic><topic>Nuclear fuels</topic><topic>Nuclear power generation</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Physics</topic><topic>Solid mechanics</topic><topic>Steel design</topic><topic>Steel tanks and pressure vessels; boiler manufacturing</topic><topic>Structural and continuum mechanics</topic><topic>Studies</topic><topic>Tubes</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>KIM, Young-Jin</creatorcontrib><creatorcontrib>KWAK, Sang-Log</creatorcontrib><creatorcontrib>LEE, Joon-Seong</creatorcontrib><creatorcontrib>PARK, Youn-Won</creatorcontrib><collection>DBPIA - 디비피아</collection><collection>DBPIA</collection><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>Materials Science & Engineering Collection</collection><collection>ProQuest Central UK/Ireland</collection><collection>ProQuest Central</collection><collection>Technology Collection</collection><collection>ProQuest One Community College</collection><collection>ProQuest Central Korea</collection><collection>Engineering Research Database</collection><collection>SciTech Premium Collection</collection><collection>ProQuest Engineering Collection</collection><collection>Engineering Database</collection><collection>ProQuest One Academic Eastern Edition (DO NOT USE)</collection><collection>ProQuest One Academic</collection><collection>ProQuest One Academic UKI Edition</collection><collection>ProQuest Central China</collection><collection>Engineering Collection</collection><collection>DELNET Engineering & Technology Collection</collection><jtitle>Journal of mechanical science and technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>KIM, Young-Jin</au><au>KWAK, Sang-Log</au><au>LEE, Joon-Seong</au><au>PARK, Youn-Won</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Integrity Evaluation System of CANDU Reactor Pressure Tube</atitle><jtitle>Journal of mechanical science and technology</jtitle><date>2003-07-01</date><risdate>2003</risdate><volume>17</volume><issue>7</issue><spage>947</spage><epage>957</epage><pages>947-957</pages><issn>1738-494X</issn><issn>1226-4865</issn><eissn>1976-3824</eissn><abstract>The pressure tube is a major component of the CANDU reactor, which supports nuclear fuel bundle. In order to complete the integrity evaluation of pressure tube, expert knowledge, iterative calculation procedures and a lot of input data are required. More over, results of integrity assessment may be different according to the evaluation method. For this reason, an integrity evaluation system, which provides efficient way of evaluation with the help of attached database, was developed. The present system was built on the basis of 3D FEM results, ASME Sec. XI, and Fitness For Service Guidelines for CANDU pressure tubes issued by the AECL (Atomic Energy Canada Limited). The present system also covers the delayed hydride cracking and the blister evaluation, which are the characteristics of pressure tube integrity evaluation. In order to verify the present system, several case studies have been performed and the results were compared with those from AECL. A good agreement was observed between those two results.</abstract><cop>Seoul</cop><pub>대한기계학회</pub><doi>10.1007/BF02982979</doi><tpages>11</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 1738-494X |
| ispartof | Journal of mechanical science and technology, 2003-07, Vol.17 (7), p.947-957 |
| issn | 1738-494X 1226-4865 1976-3824 |
| language | eng |
| recordid | cdi_proquest_miscellaneous_1266752616 |
| source | SpringerLink Journals - AutoHoldings |
| subjects | Applied sciences Blistering Candu Energy Energy. Thermal use of fuels Evaluation Exact sciences and technology Finite element method Fission nuclear power plants Fracture mechanics (crack, fatigue, damage...) Fracture mechanics, fatigue and cracks Fundamental areas of phenomenology (including applications) Heavy water reactors Installations for energy generation and conversion: thermal and electrical energy Integrity Mathematical models Mechanical engineering. Machine design Nuclear energy Nuclear fuels Nuclear power generation Nuclear reactor components Nuclear reactors Physics Solid mechanics Steel design Steel tanks and pressure vessels boiler manufacturing Structural and continuum mechanics Studies Tubes |
| title | Integrity Evaluation System of CANDU Reactor Pressure Tube |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-18T11%3A59%3A11IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-nurimedia_proqu&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Integrity%20Evaluation%20System%20of%20CANDU%20Reactor%20Pressure%20Tube&rft.jtitle=Journal%20of%20mechanical%20science%20and%20technology&rft.au=KIM,%20Young-Jin&rft.date=2003-07-01&rft.volume=17&rft.issue=7&rft.spage=947&rft.epage=957&rft.pages=947-957&rft.issn=1738-494X&rft.eissn=1976-3824&rft_id=info:doi/10.1007/BF02982979&rft_dat=%3Cnurimedia_proqu%3ENODE00531661%3C/nurimedia_proqu%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=1021003790&rft_id=info:pmid/&rft_nurid=NODE00531661&rfr_iscdi=true |