Two-dimensional resistive MHD simulation of the optimized plasma formation in the spherical tokamaks

We present 2D global MHD simulation results of the optimized start-up scenarios for the spherical tokamak to maximize the ion heating energy determined by the value of the poloidal private flux during the merging start-ups. The series of simulations has successfully revealed the dependence of the po...

Ausführliche Beschreibung

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:Nuclear fusion 2021-06, Vol.61 (6), p.66001
Hauptverfasser: Ahmadi, T., Tanabe, H., Ono, Y.
Format: Artikel
Sprache:eng
Online-Zugang:Volltext
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
container_end_page
container_issue 6
container_start_page 66001
container_title Nuclear fusion
container_volume 61
creator Ahmadi, T.
Tanabe, H.
Ono, Y.
description We present 2D global MHD simulation results of the optimized start-up scenarios for the spherical tokamak to maximize the ion heating energy determined by the value of the poloidal private flux during the merging start-ups. The series of simulations has successfully revealed the dependence of the poloidal private flux on the in-vessel poloidal coils’ separation length under the fixed amount of coils’ magnetic energy. The radial and azimuthal locations of the internal coils need to be optimized to maximize high private flux and consequently high ion heating energy. In the case of a two poloidal field (PF) coils system, the private flux and ion heating energy increase with the coils’ separation length. Installing two additional PF coils improves the private flux significantly, even if the coils’ separation length is short.
doi_str_mv 10.1088/1741-4326/abebce
format Article
fullrecord <record><control><sourceid>crossref</sourceid><recordid>TN_cdi_crossref_primary_10_1088_1741_4326_abebce</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>10_1088_1741_4326_abebce</sourcerecordid><originalsourceid>FETCH-LOGICAL-c309t-77bde58051940a076cb9c5fc7e2b14d4e8195ff8dfb16ce0b2eaccd01476e4323</originalsourceid><addsrcrecordid>eNo9kE1LxDAYhIMoWFfvHvMH6r5pm34cZf1YYcXLei75eMPGbZqSVEV_va0VTwMzw8A8hFwzuGFQ12tWFSwt8qxcC4lS4QlJ_q1TkgBkTco54-fkIsY3AFawPE-I3n_6VFuHfbS-Fx0NGG0c7QfS5-0djda9d2KcIuoNHQ9I_TBaZ79R06ET0QlqfHBLw_a_jTgcMFg1bY3-KJw4xktyZkQX8epPV-T14X6_2aa7l8enze0uVTk0Y1pVUiOvgbOmAAFVqWSjuFEVZpIVusCaNdyYWhvJSoUgMxRK6elKVeL0M18RWHZV8DEGNO0QrBPhq2XQzpTaGUk7I2kXSvkPoYdeqQ</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype></control><display><type>article</type><title>Two-dimensional resistive MHD simulation of the optimized plasma formation in the spherical tokamaks</title><source>IOP Publishing Journals</source><source>Institute of Physics (IOP) Journals - HEAL-Link</source><creator>Ahmadi, T. ; Tanabe, H. ; Ono, Y.</creator><creatorcontrib>Ahmadi, T. ; Tanabe, H. ; Ono, Y.</creatorcontrib><description>We present 2D global MHD simulation results of the optimized start-up scenarios for the spherical tokamak to maximize the ion heating energy determined by the value of the poloidal private flux during the merging start-ups. The series of simulations has successfully revealed the dependence of the poloidal private flux on the in-vessel poloidal coils’ separation length under the fixed amount of coils’ magnetic energy. The radial and azimuthal locations of the internal coils need to be optimized to maximize high private flux and consequently high ion heating energy. In the case of a two poloidal field (PF) coils system, the private flux and ion heating energy increase with the coils’ separation length. Installing two additional PF coils improves the private flux significantly, even if the coils’ separation length is short.</description><identifier>ISSN: 0029-5515</identifier><identifier>EISSN: 1741-4326</identifier><identifier>DOI: 10.1088/1741-4326/abebce</identifier><language>eng</language><ispartof>Nuclear fusion, 2021-06, Vol.61 (6), p.66001</ispartof><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c309t-77bde58051940a076cb9c5fc7e2b14d4e8195ff8dfb16ce0b2eaccd01476e4323</citedby><cites>FETCH-LOGICAL-c309t-77bde58051940a076cb9c5fc7e2b14d4e8195ff8dfb16ce0b2eaccd01476e4323</cites><orcidid>0000-0003-3566-6980</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,776,780,27901,27902</link.rule.ids></links><search><creatorcontrib>Ahmadi, T.</creatorcontrib><creatorcontrib>Tanabe, H.</creatorcontrib><creatorcontrib>Ono, Y.</creatorcontrib><title>Two-dimensional resistive MHD simulation of the optimized plasma formation in the spherical tokamaks</title><title>Nuclear fusion</title><description>We present 2D global MHD simulation results of the optimized start-up scenarios for the spherical tokamak to maximize the ion heating energy determined by the value of the poloidal private flux during the merging start-ups. The series of simulations has successfully revealed the dependence of the poloidal private flux on the in-vessel poloidal coils’ separation length under the fixed amount of coils’ magnetic energy. The radial and azimuthal locations of the internal coils need to be optimized to maximize high private flux and consequently high ion heating energy. In the case of a two poloidal field (PF) coils system, the private flux and ion heating energy increase with the coils’ separation length. Installing two additional PF coils improves the private flux significantly, even if the coils’ separation length is short.</description><issn>0029-5515</issn><issn>1741-4326</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><recordid>eNo9kE1LxDAYhIMoWFfvHvMH6r5pm34cZf1YYcXLei75eMPGbZqSVEV_va0VTwMzw8A8hFwzuGFQ12tWFSwt8qxcC4lS4QlJ_q1TkgBkTco54-fkIsY3AFawPE-I3n_6VFuHfbS-Fx0NGG0c7QfS5-0djda9d2KcIuoNHQ9I_TBaZ79R06ET0QlqfHBLw_a_jTgcMFg1bY3-KJw4xktyZkQX8epPV-T14X6_2aa7l8enze0uVTk0Y1pVUiOvgbOmAAFVqWSjuFEVZpIVusCaNdyYWhvJSoUgMxRK6elKVeL0M18RWHZV8DEGNO0QrBPhq2XQzpTaGUk7I2kXSvkPoYdeqQ</recordid><startdate>20210601</startdate><enddate>20210601</enddate><creator>Ahmadi, T.</creator><creator>Tanabe, H.</creator><creator>Ono, Y.</creator><scope>AAYXX</scope><scope>CITATION</scope><orcidid>https://orcid.org/0000-0003-3566-6980</orcidid></search><sort><creationdate>20210601</creationdate><title>Two-dimensional resistive MHD simulation of the optimized plasma formation in the spherical tokamaks</title><author>Ahmadi, T. ; Tanabe, H. ; Ono, Y.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c309t-77bde58051940a076cb9c5fc7e2b14d4e8195ff8dfb16ce0b2eaccd01476e4323</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Ahmadi, T.</creatorcontrib><creatorcontrib>Tanabe, H.</creatorcontrib><creatorcontrib>Ono, Y.</creatorcontrib><collection>CrossRef</collection><jtitle>Nuclear fusion</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Ahmadi, T.</au><au>Tanabe, H.</au><au>Ono, Y.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Two-dimensional resistive MHD simulation of the optimized plasma formation in the spherical tokamaks</atitle><jtitle>Nuclear fusion</jtitle><date>2021-06-01</date><risdate>2021</risdate><volume>61</volume><issue>6</issue><spage>66001</spage><pages>66001-</pages><issn>0029-5515</issn><eissn>1741-4326</eissn><abstract>We present 2D global MHD simulation results of the optimized start-up scenarios for the spherical tokamak to maximize the ion heating energy determined by the value of the poloidal private flux during the merging start-ups. The series of simulations has successfully revealed the dependence of the poloidal private flux on the in-vessel poloidal coils’ separation length under the fixed amount of coils’ magnetic energy. The radial and azimuthal locations of the internal coils need to be optimized to maximize high private flux and consequently high ion heating energy. In the case of a two poloidal field (PF) coils system, the private flux and ion heating energy increase with the coils’ separation length. Installing two additional PF coils improves the private flux significantly, even if the coils’ separation length is short.</abstract><doi>10.1088/1741-4326/abebce</doi><orcidid>https://orcid.org/0000-0003-3566-6980</orcidid></addata></record>
fulltext fulltext
identifier ISSN: 0029-5515
ispartof Nuclear fusion, 2021-06, Vol.61 (6), p.66001
issn 0029-5515
1741-4326
language eng
recordid cdi_crossref_primary_10_1088_1741_4326_abebce
source IOP Publishing Journals; Institute of Physics (IOP) Journals - HEAL-Link
title Two-dimensional resistive MHD simulation of the optimized plasma formation in the spherical tokamaks
url https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-02-01T18%3A54%3A35IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-crossref&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Two-dimensional%20resistive%20MHD%20simulation%20of%20the%20optimized%20plasma%20formation%20in%20the%20spherical%20tokamaks&rft.jtitle=Nuclear%20fusion&rft.au=Ahmadi,%20T.&rft.date=2021-06-01&rft.volume=61&rft.issue=6&rft.spage=66001&rft.pages=66001-&rft.issn=0029-5515&rft.eissn=1741-4326&rft_id=info:doi/10.1088/1741-4326/abebce&rft_dat=%3Ccrossref%3E10_1088_1741_4326_abebce%3C/crossref%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_id=info:pmid/&rfr_iscdi=true