Progress on source term evaluation of accidental events in the experimental fusion installation ITER
•Progress of the IRSN R&D activities related to the safety assessment of the ITER installation.•Simulation of an accidental scenario with the ASTEC code: loss of coolant in port cell and in vacuum vessel.•Location and chemical speciation of beryllium dusts and tritium. The French “Institut de Ra...
Gespeichert in:
| Veröffentlicht in: | Fusion engineering and design 2015-10, Vol.98-99, p.2219-2222 |
|---|---|
| Hauptverfasser: | , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 2222 |
|---|---|
| container_issue | |
| container_start_page | 2219 |
| container_title | Fusion engineering and design |
| container_volume | 98-99 |
| creator | Virot, F. Barrachin, M. Vola, D. |
| description | •Progress of the IRSN R&D activities related to the safety assessment of the ITER installation.•Simulation of an accidental scenario with the ASTEC code: loss of coolant in port cell and in vacuum vessel.•Location and chemical speciation of beryllium dusts and tritium.
The French “Institut de Radioprotection et de Sûreté Nucléaire” (IRSN) in support to the French nuclear safety authority performs the safety analyses of the ITER experimental installation. We present the progress in the R&D activities related to a better evaluation of the source term in the event of an accident in this installation. These improvements are illustrated by an evaluation of the source term of a LOCA transient with the dedicated ASTEC code. |
| doi_str_mv | 10.1016/j.fusengdes.2014.12.025 |
| format | Article |
| fullrecord | <record><control><sourceid>proquest_hal_p</sourceid><recordid>TN_cdi_hal_primary_oai_HAL_hal_02572546v1</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0920379614006693</els_id><sourcerecordid>1786151810</sourcerecordid><originalsourceid>FETCH-LOGICAL-c538t-5fd23f7b98a803a8dcf89a2b275b12ec641db6196a3e098bbc87c7b0cb7d05603</originalsourceid><addsrcrecordid>eNqNkcGK2zAQhsXSwqZpn6E-tgd7NVJsyccQ0s1CYEtJz0KWxomCY6WSHdq3Xxkve92CYNDMN8M_8xPyFWgBFKqHc9GOEfujxVgwCqsCWEFZeUcWIAXPBdTVB7KgNaM5F3V1Tz7FeKYURHoLYn8GfwwYY-b7LPoxGMwGDJcMb7ob9eBS2reZNsZZ7AfdpUKKMXN9Npwww79XDO4yl5KQiXd9TL9ubn46bH99Jh9b3UX88hqX5PeP7WGzy_fPj0-b9T43JZdDXraW8VY0tdSSci2taWWtWcNE2QBDU63ANlXaR3OktWwaI4URDTWNsLSsKF-S7_Pck-7UNcnS4Z_y2qndeq-mXLqLYOWqukFiv83sNfg_I8ZBXVw0mGT36MeoQMgKSpBA_wMVXK5qxsuEihk1wccYsH2TAVRNdqmzerNLTXYpYJOs1LmeOzEd6OYwqGgc9gatC2gGZb17d8YL8cejJw</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>1773849235</pqid></control><display><type>article</type><title>Progress on source term evaluation of accidental events in the experimental fusion installation ITER</title><source>ScienceDirect Journals (5 years ago - present)</source><creator>Virot, F. ; Barrachin, M. ; Vola, D.</creator><creatorcontrib>Virot, F. ; Barrachin, M. ; Vola, D.</creatorcontrib><description>•Progress of the IRSN R&D activities related to the safety assessment of the ITER installation.•Simulation of an accidental scenario with the ASTEC code: loss of coolant in port cell and in vacuum vessel.•Location and chemical speciation of beryllium dusts and tritium.
The French “Institut de Radioprotection et de Sûreté Nucléaire” (IRSN) in support to the French nuclear safety authority performs the safety analyses of the ITER experimental installation. We present the progress in the R&D activities related to a better evaluation of the source term in the event of an accident in this installation. These improvements are illustrated by an evaluation of the source term of a LOCA transient with the dedicated ASTEC code.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2014.12.025</identifier><language>eng</language><publisher>Elsevier B.V</publisher><subject>Accidents ; ASTEC ; Beryllium dust ; ITER ; LOCA ; Nuclear engineering ; Nuclear fusion ; Nuclear safety ; Physics ; Source term ; Tritium</subject><ispartof>Fusion engineering and design, 2015-10, Vol.98-99, p.2219-2222</ispartof><rights>2015 Elsevier B.V.</rights><rights>Distributed under a Creative Commons Attribution 4.0 International License</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c538t-5fd23f7b98a803a8dcf89a2b275b12ec641db6196a3e098bbc87c7b0cb7d05603</citedby><cites>FETCH-LOGICAL-c538t-5fd23f7b98a803a8dcf89a2b275b12ec641db6196a3e098bbc87c7b0cb7d05603</cites><orcidid>0000-0001-9778-7353</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.fusengdes.2014.12.025$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>230,314,780,784,885,3548,27923,27924,45994</link.rule.ids><backlink>$$Uhttps://hal.science/hal-02572546$$DView record in HAL$$Hfree_for_read</backlink></links><search><creatorcontrib>Virot, F.</creatorcontrib><creatorcontrib>Barrachin, M.</creatorcontrib><creatorcontrib>Vola, D.</creatorcontrib><title>Progress on source term evaluation of accidental events in the experimental fusion installation ITER</title><title>Fusion engineering and design</title><description>•Progress of the IRSN R&D activities related to the safety assessment of the ITER installation.•Simulation of an accidental scenario with the ASTEC code: loss of coolant in port cell and in vacuum vessel.•Location and chemical speciation of beryllium dusts and tritium.
The French “Institut de Radioprotection et de Sûreté Nucléaire” (IRSN) in support to the French nuclear safety authority performs the safety analyses of the ITER experimental installation. We present the progress in the R&D activities related to a better evaluation of the source term in the event of an accident in this installation. These improvements are illustrated by an evaluation of the source term of a LOCA transient with the dedicated ASTEC code.</description><subject>Accidents</subject><subject>ASTEC</subject><subject>Beryllium dust</subject><subject>ITER</subject><subject>LOCA</subject><subject>Nuclear engineering</subject><subject>Nuclear fusion</subject><subject>Nuclear safety</subject><subject>Physics</subject><subject>Source term</subject><subject>Tritium</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2015</creationdate><recordtype>article</recordtype><recordid>eNqNkcGK2zAQhsXSwqZpn6E-tgd7NVJsyccQ0s1CYEtJz0KWxomCY6WSHdq3Xxkve92CYNDMN8M_8xPyFWgBFKqHc9GOEfujxVgwCqsCWEFZeUcWIAXPBdTVB7KgNaM5F3V1Tz7FeKYURHoLYn8GfwwYY-b7LPoxGMwGDJcMb7ob9eBS2reZNsZZ7AfdpUKKMXN9Npwww79XDO4yl5KQiXd9TL9ubn46bH99Jh9b3UX88hqX5PeP7WGzy_fPj0-b9T43JZdDXraW8VY0tdSSci2taWWtWcNE2QBDU63ANlXaR3OktWwaI4URDTWNsLSsKF-S7_Pck-7UNcnS4Z_y2qndeq-mXLqLYOWqukFiv83sNfg_I8ZBXVw0mGT36MeoQMgKSpBA_wMVXK5qxsuEihk1wccYsH2TAVRNdqmzerNLTXYpYJOs1LmeOzEd6OYwqGgc9gatC2gGZb17d8YL8cejJw</recordid><startdate>20151001</startdate><enddate>20151001</enddate><creator>Virot, F.</creator><creator>Barrachin, M.</creator><creator>Vola, D.</creator><general>Elsevier B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7T2</scope><scope>7U2</scope><scope>C1K</scope><scope>7SP</scope><scope>7TB</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope><scope>1XC</scope><orcidid>https://orcid.org/0000-0001-9778-7353</orcidid></search><sort><creationdate>20151001</creationdate><title>Progress on source term evaluation of accidental events in the experimental fusion installation ITER</title><author>Virot, F. ; Barrachin, M. ; Vola, D.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c538t-5fd23f7b98a803a8dcf89a2b275b12ec641db6196a3e098bbc87c7b0cb7d05603</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2015</creationdate><topic>Accidents</topic><topic>ASTEC</topic><topic>Beryllium dust</topic><topic>ITER</topic><topic>LOCA</topic><topic>Nuclear engineering</topic><topic>Nuclear fusion</topic><topic>Nuclear safety</topic><topic>Physics</topic><topic>Source term</topic><topic>Tritium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Virot, F.</creatorcontrib><creatorcontrib>Barrachin, M.</creatorcontrib><creatorcontrib>Vola, D.</creatorcontrib><collection>CrossRef</collection><collection>Health and Safety Science Abstracts (Full archive)</collection><collection>Safety Science and Risk</collection><collection>Environmental Sciences and Pollution Management</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><collection>Hyper Article en Ligne (HAL)</collection><jtitle>Fusion engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Virot, F.</au><au>Barrachin, M.</au><au>Vola, D.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Progress on source term evaluation of accidental events in the experimental fusion installation ITER</atitle><jtitle>Fusion engineering and design</jtitle><date>2015-10-01</date><risdate>2015</risdate><volume>98-99</volume><spage>2219</spage><epage>2222</epage><pages>2219-2222</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>•Progress of the IRSN R&D activities related to the safety assessment of the ITER installation.•Simulation of an accidental scenario with the ASTEC code: loss of coolant in port cell and in vacuum vessel.•Location and chemical speciation of beryllium dusts and tritium.
The French “Institut de Radioprotection et de Sûreté Nucléaire” (IRSN) in support to the French nuclear safety authority performs the safety analyses of the ITER experimental installation. We present the progress in the R&D activities related to a better evaluation of the source term in the event of an accident in this installation. These improvements are illustrated by an evaluation of the source term of a LOCA transient with the dedicated ASTEC code.</abstract><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2014.12.025</doi><tpages>4</tpages><orcidid>https://orcid.org/0000-0001-9778-7353</orcidid></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0920-3796 |
| ispartof | Fusion engineering and design, 2015-10, Vol.98-99, p.2219-2222 |
| issn | 0920-3796 1873-7196 |
| language | eng |
| recordid | cdi_hal_primary_oai_HAL_hal_02572546v1 |
| source | ScienceDirect Journals (5 years ago - present) |
| subjects | Accidents ASTEC Beryllium dust ITER LOCA Nuclear engineering Nuclear fusion Nuclear safety Physics Source term Tritium |
| title | Progress on source term evaluation of accidental events in the experimental fusion installation ITER |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-10T22%3A05%3A07IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_hal_p&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Progress%20on%20source%20term%20evaluation%20of%20accidental%20events%20in%20the%20experimental%20fusion%20installation%20ITER&rft.jtitle=Fusion%20engineering%20and%20design&rft.au=Virot,%20F.&rft.date=2015-10-01&rft.volume=98-99&rft.spage=2219&rft.epage=2222&rft.pages=2219-2222&rft.issn=0920-3796&rft.eissn=1873-7196&rft_id=info:doi/10.1016/j.fusengdes.2014.12.025&rft_dat=%3Cproquest_hal_p%3E1786151810%3C/proquest_hal_p%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=1773849235&rft_id=info:pmid/&rft_els_id=S0920379614006693&rfr_iscdi=true |