Nuclear responses in the ITER IVVS port cell
•Relevant nuclear quantities in the Port Cells (PC) hosting the IVVS have been calculated by means of the MCNP Monte Carlo.•The neutron and gamma sources needed to perform the nuclear analyses include both the contribution from the radiation streaming through the Lower Port and by activated water.•A...
Gespeichert in:
| Veröffentlicht in: | Fusion engineering and design 2017-11, Vol.124, p.645-648 |
|---|---|
| Hauptverfasser: | , , , , , , , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 648 |
|---|---|
| container_issue | |
| container_start_page | 645 |
| container_title | Fusion engineering and design |
| container_volume | 124 |
| creator | Flammini, Davide Fischer, Ulrich Moro, Fabio Pampin, Raul Puiu, Adrian Qiu, Yuefeng Reichle, Roger Travleev, Anton Villari, Rosaria |
| description | •Relevant nuclear quantities in the Port Cells (PC) hosting the IVVS have been calculated by means of the MCNP Monte Carlo.•The neutron and gamma sources needed to perform the nuclear analyses include both the contribution from the radiation streaming through the Lower Port and by activated water.•Absorbed dose on sensitive components over the ITER lifetime has been calculated in the PC area, including contribution from activated water.•Shut down dose rate after 1 day has been calculated in the PC.
The ITER In-Vessel Viewing System (IVVS) consists of six identical units located at the B1 level of the Tokamak complex. In this work relevant nuclear quantities in the Port Cell (PC) have been calculated by means of the MCNP Monte Carlo code in a full 3-D geometry, including the IVVS and its shielding blocks. A comprehensive MCNP model of the PC has been developed including a detailed description of the Bioshield plug, pipes, penetrations, cask rails and PC door. The neutron and gamma sources needed to perform the nuclear analyses include both contributions from the radiation streaming through the Lower Port and activated water. Monte Carlo calculations have been performed to assess the radiation field inside the PC through maps of neutron and gamma fluxes. Absorbed dose on sensitive components over the ITER lifetime has been calculated in the PC area, in order to estimate the nuclear loads that the installed equipment has to withstand. Moreover, the shutdown dose rate distribution at 1day after shutdown has been calculated. |
| doi_str_mv | 10.1016/j.fusengdes.2017.02.033 |
| format | Article |
| fullrecord | <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_journals_2050618388</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0920379617301163</els_id><sourcerecordid>2050618388</sourcerecordid><originalsourceid>FETCH-LOGICAL-c343t-adcb0ed1dd8c560e717d63e6c908f0e4760fc1f571584390084ec1c5321a8ad23</originalsourceid><addsrcrecordid>eNqFkMFKxDAQhoMouK4-gwGvtk6SNkmPy7LqwqKg615DTabaUtuatIJvb5YVr8LAXL7_H-Yj5JJByoDJmyatpoDdm8OQcmAqBZ6CEEdkxrQSiWKFPCYzKDgkQhXylJyF0EAE48zI9cNkWyw99RiGvgsYaN3R8R3pert6ouvd7pkOvR-pxbY9JydV2Qa8-N1z8nK72i7vk83j3Xq52CRWZGJMSmdfAR1zTttcAiqmnBQobQG6AsyUhMqyKlcs15koAHSGltlccFbq0nExJ1eH3sH3nxOG0TT95Lt40nDIQTIttI6UOlDW9yF4rMzg64_SfxsGZq_GNOZPjdmrMcBNVBOTi0MS4xNfNXoTbI2dRVd7tKNxff1vxw-CtG7c</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2050618388</pqid></control><display><type>article</type><title>Nuclear responses in the ITER IVVS port cell</title><source>ScienceDirect Journals (5 years ago - present)</source><creator>Flammini, Davide ; Fischer, Ulrich ; Moro, Fabio ; Pampin, Raul ; Puiu, Adrian ; Qiu, Yuefeng ; Reichle, Roger ; Travleev, Anton ; Villari, Rosaria</creator><creatorcontrib>Flammini, Davide ; Fischer, Ulrich ; Moro, Fabio ; Pampin, Raul ; Puiu, Adrian ; Qiu, Yuefeng ; Reichle, Roger ; Travleev, Anton ; Villari, Rosaria</creatorcontrib><description>•Relevant nuclear quantities in the Port Cells (PC) hosting the IVVS have been calculated by means of the MCNP Monte Carlo.•The neutron and gamma sources needed to perform the nuclear analyses include both the contribution from the radiation streaming through the Lower Port and by activated water.•Absorbed dose on sensitive components over the ITER lifetime has been calculated in the PC area, including contribution from activated water.•Shut down dose rate after 1 day has been calculated in the PC.
The ITER In-Vessel Viewing System (IVVS) consists of six identical units located at the B1 level of the Tokamak complex. In this work relevant nuclear quantities in the Port Cell (PC) have been calculated by means of the MCNP Monte Carlo code in a full 3-D geometry, including the IVVS and its shielding blocks. A comprehensive MCNP model of the PC has been developed including a detailed description of the Bioshield plug, pipes, penetrations, cask rails and PC door. The neutron and gamma sources needed to perform the nuclear analyses include both contributions from the radiation streaming through the Lower Port and activated water. Monte Carlo calculations have been performed to assess the radiation field inside the PC through maps of neutron and gamma fluxes. Absorbed dose on sensitive components over the ITER lifetime has been calculated in the PC area, in order to estimate the nuclear loads that the installed equipment has to withstand. Moreover, the shutdown dose rate distribution at 1day after shutdown has been calculated.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2017.02.033</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Activation diagnostic ; Computer simulation ; Dosage ; Fluxes ; Fusion ; ITER ; Neutrons ; Nuclear analysis ; Plasma ; Port cell ; Radiation ; Radiation shielding ; Shutdowns ; Tokamak devices</subject><ispartof>Fusion engineering and design, 2017-11, Vol.124, p.645-648</ispartof><rights>2017 Elsevier B.V.</rights><rights>Copyright Elsevier Science Ltd. Nov 2017</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c343t-adcb0ed1dd8c560e717d63e6c908f0e4760fc1f571584390084ec1c5321a8ad23</citedby><cites>FETCH-LOGICAL-c343t-adcb0ed1dd8c560e717d63e6c908f0e4760fc1f571584390084ec1c5321a8ad23</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.fusengdes.2017.02.033$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3550,27924,27925,45995</link.rule.ids></links><search><creatorcontrib>Flammini, Davide</creatorcontrib><creatorcontrib>Fischer, Ulrich</creatorcontrib><creatorcontrib>Moro, Fabio</creatorcontrib><creatorcontrib>Pampin, Raul</creatorcontrib><creatorcontrib>Puiu, Adrian</creatorcontrib><creatorcontrib>Qiu, Yuefeng</creatorcontrib><creatorcontrib>Reichle, Roger</creatorcontrib><creatorcontrib>Travleev, Anton</creatorcontrib><creatorcontrib>Villari, Rosaria</creatorcontrib><title>Nuclear responses in the ITER IVVS port cell</title><title>Fusion engineering and design</title><description>•Relevant nuclear quantities in the Port Cells (PC) hosting the IVVS have been calculated by means of the MCNP Monte Carlo.•The neutron and gamma sources needed to perform the nuclear analyses include both the contribution from the radiation streaming through the Lower Port and by activated water.•Absorbed dose on sensitive components over the ITER lifetime has been calculated in the PC area, including contribution from activated water.•Shut down dose rate after 1 day has been calculated in the PC.
The ITER In-Vessel Viewing System (IVVS) consists of six identical units located at the B1 level of the Tokamak complex. In this work relevant nuclear quantities in the Port Cell (PC) have been calculated by means of the MCNP Monte Carlo code in a full 3-D geometry, including the IVVS and its shielding blocks. A comprehensive MCNP model of the PC has been developed including a detailed description of the Bioshield plug, pipes, penetrations, cask rails and PC door. The neutron and gamma sources needed to perform the nuclear analyses include both contributions from the radiation streaming through the Lower Port and activated water. Monte Carlo calculations have been performed to assess the radiation field inside the PC through maps of neutron and gamma fluxes. Absorbed dose on sensitive components over the ITER lifetime has been calculated in the PC area, in order to estimate the nuclear loads that the installed equipment has to withstand. Moreover, the shutdown dose rate distribution at 1day after shutdown has been calculated.</description><subject>Activation diagnostic</subject><subject>Computer simulation</subject><subject>Dosage</subject><subject>Fluxes</subject><subject>Fusion</subject><subject>ITER</subject><subject>Neutrons</subject><subject>Nuclear analysis</subject><subject>Plasma</subject><subject>Port cell</subject><subject>Radiation</subject><subject>Radiation shielding</subject><subject>Shutdowns</subject><subject>Tokamak devices</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2017</creationdate><recordtype>article</recordtype><recordid>eNqFkMFKxDAQhoMouK4-gwGvtk6SNkmPy7LqwqKg615DTabaUtuatIJvb5YVr8LAXL7_H-Yj5JJByoDJmyatpoDdm8OQcmAqBZ6CEEdkxrQSiWKFPCYzKDgkQhXylJyF0EAE48zI9cNkWyw99RiGvgsYaN3R8R3pert6ouvd7pkOvR-pxbY9JydV2Qa8-N1z8nK72i7vk83j3Xq52CRWZGJMSmdfAR1zTttcAiqmnBQobQG6AsyUhMqyKlcs15koAHSGltlccFbq0nExJ1eH3sH3nxOG0TT95Lt40nDIQTIttI6UOlDW9yF4rMzg64_SfxsGZq_GNOZPjdmrMcBNVBOTi0MS4xNfNXoTbI2dRVd7tKNxff1vxw-CtG7c</recordid><startdate>201711</startdate><enddate>201711</enddate><creator>Flammini, Davide</creator><creator>Fischer, Ulrich</creator><creator>Moro, Fabio</creator><creator>Pampin, Raul</creator><creator>Puiu, Adrian</creator><creator>Qiu, Yuefeng</creator><creator>Reichle, Roger</creator><creator>Travleev, Anton</creator><creator>Villari, Rosaria</creator><general>Elsevier B.V</general><general>Elsevier Science Ltd</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>H8D</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>201711</creationdate><title>Nuclear responses in the ITER IVVS port cell</title><author>Flammini, Davide ; Fischer, Ulrich ; Moro, Fabio ; Pampin, Raul ; Puiu, Adrian ; Qiu, Yuefeng ; Reichle, Roger ; Travleev, Anton ; Villari, Rosaria</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c343t-adcb0ed1dd8c560e717d63e6c908f0e4760fc1f571584390084ec1c5321a8ad23</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2017</creationdate><topic>Activation diagnostic</topic><topic>Computer simulation</topic><topic>Dosage</topic><topic>Fluxes</topic><topic>Fusion</topic><topic>ITER</topic><topic>Neutrons</topic><topic>Nuclear analysis</topic><topic>Plasma</topic><topic>Port cell</topic><topic>Radiation</topic><topic>Radiation shielding</topic><topic>Shutdowns</topic><topic>Tokamak devices</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Flammini, Davide</creatorcontrib><creatorcontrib>Fischer, Ulrich</creatorcontrib><creatorcontrib>Moro, Fabio</creatorcontrib><creatorcontrib>Pampin, Raul</creatorcontrib><creatorcontrib>Puiu, Adrian</creatorcontrib><creatorcontrib>Qiu, Yuefeng</creatorcontrib><creatorcontrib>Reichle, Roger</creatorcontrib><creatorcontrib>Travleev, Anton</creatorcontrib><creatorcontrib>Villari, Rosaria</creatorcontrib><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Aerospace 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>Flammini, Davide</au><au>Fischer, Ulrich</au><au>Moro, Fabio</au><au>Pampin, Raul</au><au>Puiu, Adrian</au><au>Qiu, Yuefeng</au><au>Reichle, Roger</au><au>Travleev, Anton</au><au>Villari, Rosaria</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Nuclear responses in the ITER IVVS port cell</atitle><jtitle>Fusion engineering and design</jtitle><date>2017-11</date><risdate>2017</risdate><volume>124</volume><spage>645</spage><epage>648</epage><pages>645-648</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>•Relevant nuclear quantities in the Port Cells (PC) hosting the IVVS have been calculated by means of the MCNP Monte Carlo.•The neutron and gamma sources needed to perform the nuclear analyses include both the contribution from the radiation streaming through the Lower Port and by activated water.•Absorbed dose on sensitive components over the ITER lifetime has been calculated in the PC area, including contribution from activated water.•Shut down dose rate after 1 day has been calculated in the PC.
The ITER In-Vessel Viewing System (IVVS) consists of six identical units located at the B1 level of the Tokamak complex. In this work relevant nuclear quantities in the Port Cell (PC) have been calculated by means of the MCNP Monte Carlo code in a full 3-D geometry, including the IVVS and its shielding blocks. A comprehensive MCNP model of the PC has been developed including a detailed description of the Bioshield plug, pipes, penetrations, cask rails and PC door. The neutron and gamma sources needed to perform the nuclear analyses include both contributions from the radiation streaming through the Lower Port and activated water. Monte Carlo calculations have been performed to assess the radiation field inside the PC through maps of neutron and gamma fluxes. Absorbed dose on sensitive components over the ITER lifetime has been calculated in the PC area, in order to estimate the nuclear loads that the installed equipment has to withstand. Moreover, the shutdown dose rate distribution at 1day after shutdown has been calculated.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2017.02.033</doi><tpages>4</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0920-3796 |
| ispartof | Fusion engineering and design, 2017-11, Vol.124, p.645-648 |
| issn | 0920-3796 1873-7196 |
| language | eng |
| recordid | cdi_proquest_journals_2050618388 |
| source | ScienceDirect Journals (5 years ago - present) |
| subjects | Activation diagnostic Computer simulation Dosage Fluxes Fusion ITER Neutrons Nuclear analysis Plasma Port cell Radiation Radiation shielding Shutdowns Tokamak devices |
| title | Nuclear responses in the ITER IVVS port cell |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-29T15%3A52%3A06IST&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=Nuclear%20responses%20in%20the%20ITER%20IVVS%20port%20cell&rft.jtitle=Fusion%20engineering%20and%20design&rft.au=Flammini,%20Davide&rft.date=2017-11&rft.volume=124&rft.spage=645&rft.epage=648&rft.pages=645-648&rft.issn=0920-3796&rft.eissn=1873-7196&rft_id=info:doi/10.1016/j.fusengdes.2017.02.033&rft_dat=%3Cproquest_cross%3E2050618388%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=2050618388&rft_id=info:pmid/&rft_els_id=S0920379617301163&rfr_iscdi=true |