Loading…

Tests of the cryogenic target for lithium and hydrogen isotopes extraction from the chamber of T-11M tokamak without its venting

•We tested the cryogenic target as pump of Li ions sputtered from tokamak chamber by glow discharge.•We found a positive effect on the Li collection an addition of the residual gases to glow discharge.•Cooled target can be used during plasma operation to collect and remove Li and H from tokamak cham...

Full description

Saved in:
Bibliographic Details
Published in:Fusion engineering and design 2014-12, Vol.89 (12), p.2923-2929
Main Authors: Mirnov, Sergey V., Djigailo, Nadejda T., Dzhurik, Sergey P., Kostina, Anastasiya N., Kravchuk, Sergey I., Lazarev, Vladimir B., Lyublinski, Igor E., Nesterenko, Vladislav M., Petrov, Yuri V., Vertkov, Aleksei V., Zharkov, Mikhail Yu
Format: Article
Language:English
Subjects:
Citations: Items that this one cites
Items that cite this one
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
cited_by cdi_FETCH-LOGICAL-c451t-701fc88a529b43b6994b15684fa37550100ea6d82ca59c5cf27fb0cabbdaf0543
cites cdi_FETCH-LOGICAL-c451t-701fc88a529b43b6994b15684fa37550100ea6d82ca59c5cf27fb0cabbdaf0543
container_end_page 2929
container_issue 12
container_start_page 2923
container_title Fusion engineering and design
container_volume 89
creator Mirnov, Sergey V.
Djigailo, Nadejda T.
Dzhurik, Sergey P.
Kostina, Anastasiya N.
Kravchuk, Sergey I.
Lazarev, Vladimir B.
Lyublinski, Igor E.
Nesterenko, Vladislav M.
Petrov, Yuri V.
Vertkov, Aleksei V.
Zharkov, Mikhail Yu
description •We tested the cryogenic target as pump of Li ions sputtered from tokamak chamber by glow discharge.•We found a positive effect on the Li collection an addition of the residual gases to glow discharge.•Cooled target can be used during plasma operation to collect and remove Li and H from tokamak chamber. T-11M lithium program is focused on a solution of technological issues of a steady-state tokamak with liquid lithium plasma facing components (PFC). Lithium, collected by the chamber wall of such tokamak is able to capture a considerable amount of tritium, which is unacceptable. In order to restrict the level of lithium deposited on the chamber wall and captured tritium it was suggested early to use a cryogenic target technique. Such target placed in the plasma of glow discharge (GDH, He or Ar) during the tokamak conditioning can play the role of collector of lithium and tritium atoms which were sputtered by GD bombardment of the wall. The collected lithium and tritium can be evacuated mechanically together with target from tokamak chamber through vacuum lock without venting. Cryogenic target, cooled by liquid nitrogen (LN), was installed in the T-11M and tested in different modes of wall conditioning and tokamak operations. The maximum speed of the lithium collection during GDH was 3.5mg/h, that corresponds “to contamination” of wall by lithium during approximately 200 regular shots of T-11M which are equivalent to two-week regular operations. It was established that considerable part of lithium was collected in ionized state. On this basis it can be suggested the creation in tokamak chamber an equivalent ionic pump for extraction both lithium and tritium from chamber without venting during regular tokamak operation.
doi_str_mv 10.1016/j.fusengdes.2014.07.021
format article
fullrecord <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_miscellaneous_1660049001</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0920379614005298</els_id><sourcerecordid>1660049001</sourcerecordid><originalsourceid>FETCH-LOGICAL-c451t-701fc88a529b43b6994b15684fa37550100ea6d82ca59c5cf27fb0cabbdaf0543</originalsourceid><addsrcrecordid>eNqFkE1PwzAMhiMEEmPwG8iRS4vTr7RHhPiShriMc5SmzpZtbUaSDnbjp5NpiCuSJV9eP7YfQq4ZpAxYdbtK9ehxWHTo0wxYkQJPIWMnZMJqniecNdUpmUCTQZLzpjonF96vABiPNSHfc_TBU6tpWCJVbm8XOBhFg3QLDFRbRzcmLM3YUzl0dLnv3CFBjbfBbtFT_ApOqmDsQLWz_RGzlH2L7kCdJ4y90mDXspdr-hlRdgzUxJU7HIIZFpfkTMuNx6vfPiXvjw_z--dk9vb0cn83S1RRspDEa7Wqa1lmTVvkbdU0RcvKqi60zHlZAgNAWXV1pmTZqFLpjOsWlGzbTmooi3xKbo7crbMfY3xa9MYr3GzkgHb0glUVQNFEMTHKj1HlrPcOtdg600u3FwzEwblYiT_n4uBcABfReZy8O05i_GRn0AmvDA4KO-NQBdFZ8y_jB_aWkUY</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>1660049001</pqid></control><display><type>article</type><title>Tests of the cryogenic target for lithium and hydrogen isotopes extraction from the chamber of T-11M tokamak without its venting</title><source>ScienceDirect Journals</source><creator>Mirnov, Sergey V. ; Djigailo, Nadejda T. ; Dzhurik, Sergey P. ; Kostina, Anastasiya N. ; Kravchuk, Sergey I. ; Lazarev, Vladimir B. ; Lyublinski, Igor E. ; Nesterenko, Vladislav M. ; Petrov, Yuri V. ; Vertkov, Aleksei V. ; Zharkov, Mikhail Yu</creator><creatorcontrib>Mirnov, Sergey V. ; Djigailo, Nadejda T. ; Dzhurik, Sergey P. ; Kostina, Anastasiya N. ; Kravchuk, Sergey I. ; Lazarev, Vladimir B. ; Lyublinski, Igor E. ; Nesterenko, Vladislav M. ; Petrov, Yuri V. ; Vertkov, Aleksei V. ; Zharkov, Mikhail Yu</creatorcontrib><description>•We tested the cryogenic target as pump of Li ions sputtered from tokamak chamber by glow discharge.•We found a positive effect on the Li collection an addition of the residual gases to glow discharge.•Cooled target can be used during plasma operation to collect and remove Li and H from tokamak chamber. T-11M lithium program is focused on a solution of technological issues of a steady-state tokamak with liquid lithium plasma facing components (PFC). Lithium, collected by the chamber wall of such tokamak is able to capture a considerable amount of tritium, which is unacceptable. In order to restrict the level of lithium deposited on the chamber wall and captured tritium it was suggested early to use a cryogenic target technique. Such target placed in the plasma of glow discharge (GDH, He or Ar) during the tokamak conditioning can play the role of collector of lithium and tritium atoms which were sputtered by GD bombardment of the wall. The collected lithium and tritium can be evacuated mechanically together with target from tokamak chamber through vacuum lock without venting. Cryogenic target, cooled by liquid nitrogen (LN), was installed in the T-11M and tested in different modes of wall conditioning and tokamak operations. The maximum speed of the lithium collection during GDH was 3.5mg/h, that corresponds “to contamination” of wall by lithium during approximately 200 regular shots of T-11M which are equivalent to two-week regular operations. It was established that considerable part of lithium was collected in ionized state. On this basis it can be suggested the creation in tokamak chamber an equivalent ionic pump for extraction both lithium and tritium from chamber without venting during regular tokamak operation.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2014.07.021</identifier><language>eng</language><publisher>Elsevier B.V</publisher><subject>Chambers ; Conditioning ; Cryogenic target ; Equivalence ; Extraction ; Lithium ; Tokamak ; Tokamak devices ; Tritium ; Walls</subject><ispartof>Fusion engineering and design, 2014-12, Vol.89 (12), p.2923-2929</ispartof><rights>2014 Elsevier B.V.</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c451t-701fc88a529b43b6994b15684fa37550100ea6d82ca59c5cf27fb0cabbdaf0543</citedby><cites>FETCH-LOGICAL-c451t-701fc88a529b43b6994b15684fa37550100ea6d82ca59c5cf27fb0cabbdaf0543</cites><orcidid>0000-0001-5921-1249 ; 0000-0001-8701-228X</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27924,27925</link.rule.ids></links><search><creatorcontrib>Mirnov, Sergey V.</creatorcontrib><creatorcontrib>Djigailo, Nadejda T.</creatorcontrib><creatorcontrib>Dzhurik, Sergey P.</creatorcontrib><creatorcontrib>Kostina, Anastasiya N.</creatorcontrib><creatorcontrib>Kravchuk, Sergey I.</creatorcontrib><creatorcontrib>Lazarev, Vladimir B.</creatorcontrib><creatorcontrib>Lyublinski, Igor E.</creatorcontrib><creatorcontrib>Nesterenko, Vladislav M.</creatorcontrib><creatorcontrib>Petrov, Yuri V.</creatorcontrib><creatorcontrib>Vertkov, Aleksei V.</creatorcontrib><creatorcontrib>Zharkov, Mikhail Yu</creatorcontrib><title>Tests of the cryogenic target for lithium and hydrogen isotopes extraction from the chamber of T-11M tokamak without its venting</title><title>Fusion engineering and design</title><description>•We tested the cryogenic target as pump of Li ions sputtered from tokamak chamber by glow discharge.•We found a positive effect on the Li collection an addition of the residual gases to glow discharge.•Cooled target can be used during plasma operation to collect and remove Li and H from tokamak chamber. T-11M lithium program is focused on a solution of technological issues of a steady-state tokamak with liquid lithium plasma facing components (PFC). Lithium, collected by the chamber wall of such tokamak is able to capture a considerable amount of tritium, which is unacceptable. In order to restrict the level of lithium deposited on the chamber wall and captured tritium it was suggested early to use a cryogenic target technique. Such target placed in the plasma of glow discharge (GDH, He or Ar) during the tokamak conditioning can play the role of collector of lithium and tritium atoms which were sputtered by GD bombardment of the wall. The collected lithium and tritium can be evacuated mechanically together with target from tokamak chamber through vacuum lock without venting. Cryogenic target, cooled by liquid nitrogen (LN), was installed in the T-11M and tested in different modes of wall conditioning and tokamak operations. The maximum speed of the lithium collection during GDH was 3.5mg/h, that corresponds “to contamination” of wall by lithium during approximately 200 regular shots of T-11M which are equivalent to two-week regular operations. It was established that considerable part of lithium was collected in ionized state. On this basis it can be suggested the creation in tokamak chamber an equivalent ionic pump for extraction both lithium and tritium from chamber without venting during regular tokamak operation.</description><subject>Chambers</subject><subject>Conditioning</subject><subject>Cryogenic target</subject><subject>Equivalence</subject><subject>Extraction</subject><subject>Lithium</subject><subject>Tokamak</subject><subject>Tokamak devices</subject><subject>Tritium</subject><subject>Walls</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2014</creationdate><recordtype>article</recordtype><recordid>eNqFkE1PwzAMhiMEEmPwG8iRS4vTr7RHhPiShriMc5SmzpZtbUaSDnbjp5NpiCuSJV9eP7YfQq4ZpAxYdbtK9ehxWHTo0wxYkQJPIWMnZMJqniecNdUpmUCTQZLzpjonF96vABiPNSHfc_TBU6tpWCJVbm8XOBhFg3QLDFRbRzcmLM3YUzl0dLnv3CFBjbfBbtFT_ApOqmDsQLWz_RGzlH2L7kCdJ4y90mDXspdr-hlRdgzUxJU7HIIZFpfkTMuNx6vfPiXvjw_z--dk9vb0cn83S1RRspDEa7Wqa1lmTVvkbdU0RcvKqi60zHlZAgNAWXV1pmTZqFLpjOsWlGzbTmooi3xKbo7crbMfY3xa9MYr3GzkgHb0glUVQNFEMTHKj1HlrPcOtdg600u3FwzEwblYiT_n4uBcABfReZy8O05i_GRn0AmvDA4KO-NQBdFZ8y_jB_aWkUY</recordid><startdate>20141201</startdate><enddate>20141201</enddate><creator>Mirnov, Sergey V.</creator><creator>Djigailo, Nadejda T.</creator><creator>Dzhurik, Sergey P.</creator><creator>Kostina, Anastasiya N.</creator><creator>Kravchuk, Sergey I.</creator><creator>Lazarev, Vladimir B.</creator><creator>Lyublinski, Igor E.</creator><creator>Nesterenko, Vladislav M.</creator><creator>Petrov, Yuri V.</creator><creator>Vertkov, Aleksei V.</creator><creator>Zharkov, Mikhail Yu</creator><general>Elsevier B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7TB</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope><orcidid>https://orcid.org/0000-0001-5921-1249</orcidid><orcidid>https://orcid.org/0000-0001-8701-228X</orcidid></search><sort><creationdate>20141201</creationdate><title>Tests of the cryogenic target for lithium and hydrogen isotopes extraction from the chamber of T-11M tokamak without its venting</title><author>Mirnov, Sergey V. ; Djigailo, Nadejda T. ; Dzhurik, Sergey P. ; Kostina, Anastasiya N. ; Kravchuk, Sergey I. ; Lazarev, Vladimir B. ; Lyublinski, Igor E. ; Nesterenko, Vladislav M. ; Petrov, Yuri V. ; Vertkov, Aleksei V. ; Zharkov, Mikhail Yu</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c451t-701fc88a529b43b6994b15684fa37550100ea6d82ca59c5cf27fb0cabbdaf0543</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2014</creationdate><topic>Chambers</topic><topic>Conditioning</topic><topic>Cryogenic target</topic><topic>Equivalence</topic><topic>Extraction</topic><topic>Lithium</topic><topic>Tokamak</topic><topic>Tokamak devices</topic><topic>Tritium</topic><topic>Walls</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Mirnov, Sergey V.</creatorcontrib><creatorcontrib>Djigailo, Nadejda T.</creatorcontrib><creatorcontrib>Dzhurik, Sergey P.</creatorcontrib><creatorcontrib>Kostina, Anastasiya N.</creatorcontrib><creatorcontrib>Kravchuk, Sergey I.</creatorcontrib><creatorcontrib>Lazarev, Vladimir B.</creatorcontrib><creatorcontrib>Lyublinski, Igor E.</creatorcontrib><creatorcontrib>Nesterenko, Vladislav M.</creatorcontrib><creatorcontrib>Petrov, Yuri V.</creatorcontrib><creatorcontrib>Vertkov, Aleksei V.</creatorcontrib><creatorcontrib>Zharkov, Mikhail Yu</creatorcontrib><collection>CrossRef</collection><collection>Electronics &amp; Communications Abstracts</collection><collection>Mechanical &amp; 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><jtitle>Fusion engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Mirnov, Sergey V.</au><au>Djigailo, Nadejda T.</au><au>Dzhurik, Sergey P.</au><au>Kostina, Anastasiya N.</au><au>Kravchuk, Sergey I.</au><au>Lazarev, Vladimir B.</au><au>Lyublinski, Igor E.</au><au>Nesterenko, Vladislav M.</au><au>Petrov, Yuri V.</au><au>Vertkov, Aleksei V.</au><au>Zharkov, Mikhail Yu</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Tests of the cryogenic target for lithium and hydrogen isotopes extraction from the chamber of T-11M tokamak without its venting</atitle><jtitle>Fusion engineering and design</jtitle><date>2014-12-01</date><risdate>2014</risdate><volume>89</volume><issue>12</issue><spage>2923</spage><epage>2929</epage><pages>2923-2929</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>•We tested the cryogenic target as pump of Li ions sputtered from tokamak chamber by glow discharge.•We found a positive effect on the Li collection an addition of the residual gases to glow discharge.•Cooled target can be used during plasma operation to collect and remove Li and H from tokamak chamber. T-11M lithium program is focused on a solution of technological issues of a steady-state tokamak with liquid lithium plasma facing components (PFC). Lithium, collected by the chamber wall of such tokamak is able to capture a considerable amount of tritium, which is unacceptable. In order to restrict the level of lithium deposited on the chamber wall and captured tritium it was suggested early to use a cryogenic target technique. Such target placed in the plasma of glow discharge (GDH, He or Ar) during the tokamak conditioning can play the role of collector of lithium and tritium atoms which were sputtered by GD bombardment of the wall. The collected lithium and tritium can be evacuated mechanically together with target from tokamak chamber through vacuum lock without venting. Cryogenic target, cooled by liquid nitrogen (LN), was installed in the T-11M and tested in different modes of wall conditioning and tokamak operations. The maximum speed of the lithium collection during GDH was 3.5mg/h, that corresponds “to contamination” of wall by lithium during approximately 200 regular shots of T-11M which are equivalent to two-week regular operations. It was established that considerable part of lithium was collected in ionized state. On this basis it can be suggested the creation in tokamak chamber an equivalent ionic pump for extraction both lithium and tritium from chamber without venting during regular tokamak operation.</abstract><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2014.07.021</doi><tpages>7</tpages><orcidid>https://orcid.org/0000-0001-5921-1249</orcidid><orcidid>https://orcid.org/0000-0001-8701-228X</orcidid></addata></record>
fulltext fulltext
identifier ISSN: 0920-3796
ispartof Fusion engineering and design, 2014-12, Vol.89 (12), p.2923-2929
issn 0920-3796
1873-7196
language eng
recordid cdi_proquest_miscellaneous_1660049001
source ScienceDirect Journals
subjects Chambers
Conditioning
Cryogenic target
Equivalence
Extraction
Lithium
Tokamak
Tokamak devices
Tritium
Walls
title Tests of the cryogenic target for lithium and hydrogen isotopes extraction from the chamber of T-11M tokamak without its venting
url http://sfxeu10.hosted.exlibrisgroup.com/loughborough?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-29T06%3A23%3A01IST&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=Tests%20of%20the%20cryogenic%20target%20for%20lithium%20and%20hydrogen%20isotopes%20extraction%20from%20the%20chamber%20of%20T-11M%20tokamak%20without%20its%20venting&rft.jtitle=Fusion%20engineering%20and%20design&rft.au=Mirnov,%20Sergey%20V.&rft.date=2014-12-01&rft.volume=89&rft.issue=12&rft.spage=2923&rft.epage=2929&rft.pages=2923-2929&rft.issn=0920-3796&rft.eissn=1873-7196&rft_id=info:doi/10.1016/j.fusengdes.2014.07.021&rft_dat=%3Cproquest_cross%3E1660049001%3C/proquest_cross%3E%3Cgrp_id%3Ecdi_FETCH-LOGICAL-c451t-701fc88a529b43b6994b15684fa37550100ea6d82ca59c5cf27fb0cabbdaf0543%3C/grp_id%3E%3Coa%3E%3C/oa%3E%3Curl%3E%3C/url%3E&rft_id=info:oai/&rft_pqid=1660049001&rft_id=info:pmid/&rfr_iscdi=true