On monitoring the tritium breeder in a lead–lithium cooled ceramic breeder (LLCB) module of the ITER
The operation of a tritium breeder is a most process among engineering problems of DEMO. In this study, a design for monitoring tritium-breeding in the reactor is discussed. Additionally, a system for the experimental estimation of the tritium-breeding ratio (TBR) and the tritium-breeding dynamics i...
Gespeichert in:
Veröffentlicht in: | Fusion engineering and design 2012-08, Vol.87 (5-6), p.712-717 |
---|---|
Hauptverfasser: | , , , , , , , , |
Format: | Artikel |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
container_end_page | 717 |
---|---|
container_issue | 5-6 |
container_start_page | 712 |
container_title | Fusion engineering and design |
container_volume | 87 |
creator | Kapyshev, V. Kartashev, I. Kovalenko, V. Leshukov, A. Poliksha, V. Rasmerov, A. Strebkov, Yu Yukhnov, N. Vladimirova, N. |
description | The operation of a tritium breeder is a most process among engineering problems of DEMO. In this study, a design for monitoring tritium-breeding in the reactor is discussed. Additionally, a system for the experimental estimation of the tritium-breeding ratio (TBR) and the tritium-breeding dynamics in a lead–lithium cooled ceramic breeder (LLCB) test module used in the ITER is proposed. The systems are based on tritium and neutron-flux measurements under the ITER plasma D–T experiments and the use of lithium ortho-silicate and lithium carbonate samples and neutron detectors. Different lithum-6 and lithium-7 isotope contents in the samples are used to measure neutron spectrum. The samples and detectors are delivered in containers to the test breeder module (TBM) on a monitor channel connecting the TBM to an operating zone of the ITER. The tritium content in the samples is measured in a laboratory by the liquid scintillation method.
Pneumatic control is used to deliver the samples to the TBM and to extract the samples using the channel during plasma-operational pauses. Neutron calculation is performed to estimate the tritium content in the samples and the heat distribution in the materials of the channel under reactor irradiation. A measurement accuracy of the tritium content in the carbonate and orthosilicate samples can attain a level of 7% and 10%, respectively. The results of the channel-cooling calculation performed under the nominal operating conditions of the TBM (a plasma pulse) are presented in the paper. |
doi_str_mv | 10.1016/j.fusengdes.2012.02.008 |
format | Article |
fullrecord | <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_miscellaneous_1671459906</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0920379612000634</els_id><sourcerecordid>1671459906</sourcerecordid><originalsourceid>FETCH-LOGICAL-c348t-6b69225e42ab30491512647209e032d15592d778a4e1bc4a88727ec73a7fbf6c3</originalsourceid><addsrcrecordid>eNqFkMFKxDAYhIMouK4-gznqoWuStklz1GXVhQVB9BzS5O-apW00SQVvvoNv6JPYdWWvwsAc_pkP_kHonJIZJZRfbWbNEKFfW4gzRiibkVGkOkATWok8E1TyQzQhkpEsF5Ifo5MYN4RQMWqCmoced753yQfXr3F6AZyCS27ocB0ALATseqxxC9p-f361Lr1sb8b7Fiw2EHTnzD56sVrNby5HoB1awL755S2fFo-n6KjRbYSzP5-i59vF0_w-Wz3cLefXq8zkRZUyXnPJWAkF03VOCklLynghGJFAcmZpWUpmhah0AbQ2ha4qwQQYkWvR1A03-RRd7Livwb8NEJPqXDTQtroHP0RFuaBFKSXhY1Tsoib4GAM06jW4TocPRYnaLqs2ar-s2i6ryChSjc3rXRPGT94dBBWNg96AdQFMUta7fxk_OUCF5g</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>1671459906</pqid></control><display><type>article</type><title>On monitoring the tritium breeder in a lead–lithium cooled ceramic breeder (LLCB) module of the ITER</title><source>Elsevier ScienceDirect Journals</source><creator>Kapyshev, V. ; Kartashev, I. ; Kovalenko, V. ; Leshukov, A. ; Poliksha, V. ; Rasmerov, A. ; Strebkov, Yu ; Yukhnov, N. ; Vladimirova, N.</creator><creatorcontrib>Kapyshev, V. ; Kartashev, I. ; Kovalenko, V. ; Leshukov, A. ; Poliksha, V. ; Rasmerov, A. ; Strebkov, Yu ; Yukhnov, N. ; Vladimirova, N.</creatorcontrib><description>The operation of a tritium breeder is a most process among engineering problems of DEMO. In this study, a design for monitoring tritium-breeding in the reactor is discussed. Additionally, a system for the experimental estimation of the tritium-breeding ratio (TBR) and the tritium-breeding dynamics in a lead–lithium cooled ceramic breeder (LLCB) test module used in the ITER is proposed. The systems are based on tritium and neutron-flux measurements under the ITER plasma D–T experiments and the use of lithium ortho-silicate and lithium carbonate samples and neutron detectors. Different lithum-6 and lithium-7 isotope contents in the samples are used to measure neutron spectrum. The samples and detectors are delivered in containers to the test breeder module (TBM) on a monitor channel connecting the TBM to an operating zone of the ITER. The tritium content in the samples is measured in a laboratory by the liquid scintillation method.
Pneumatic control is used to deliver the samples to the TBM and to extract the samples using the channel during plasma-operational pauses. Neutron calculation is performed to estimate the tritium content in the samples and the heat distribution in the materials of the channel under reactor irradiation. A measurement accuracy of the tritium content in the carbonate and orthosilicate samples can attain a level of 7% and 10%, respectively. The results of the channel-cooling calculation performed under the nominal operating conditions of the TBM (a plasma pulse) are presented in the paper.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2012.02.008</identifier><language>eng</language><publisher>Elsevier B.V</publisher><subject>Blanket ; Ceramics ; Channels ; Design engineering ; Dynamical systems ; Dynamics ; Fusion reactor ; Lithium ; Modules ; Monitoring ; Tritium</subject><ispartof>Fusion engineering and design, 2012-08, Vol.87 (5-6), p.712-717</ispartof><rights>2012 Elsevier B.V.</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c348t-6b69225e42ab30491512647209e032d15592d778a4e1bc4a88727ec73a7fbf6c3</citedby><cites>FETCH-LOGICAL-c348t-6b69225e42ab30491512647209e032d15592d778a4e1bc4a88727ec73a7fbf6c3</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.2012.02.008$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,777,781,3537,27905,27906,45976</link.rule.ids></links><search><creatorcontrib>Kapyshev, V.</creatorcontrib><creatorcontrib>Kartashev, I.</creatorcontrib><creatorcontrib>Kovalenko, V.</creatorcontrib><creatorcontrib>Leshukov, A.</creatorcontrib><creatorcontrib>Poliksha, V.</creatorcontrib><creatorcontrib>Rasmerov, A.</creatorcontrib><creatorcontrib>Strebkov, Yu</creatorcontrib><creatorcontrib>Yukhnov, N.</creatorcontrib><creatorcontrib>Vladimirova, N.</creatorcontrib><title>On monitoring the tritium breeder in a lead–lithium cooled ceramic breeder (LLCB) module of the ITER</title><title>Fusion engineering and design</title><description>The operation of a tritium breeder is a most process among engineering problems of DEMO. In this study, a design for monitoring tritium-breeding in the reactor is discussed. Additionally, a system for the experimental estimation of the tritium-breeding ratio (TBR) and the tritium-breeding dynamics in a lead–lithium cooled ceramic breeder (LLCB) test module used in the ITER is proposed. The systems are based on tritium and neutron-flux measurements under the ITER plasma D–T experiments and the use of lithium ortho-silicate and lithium carbonate samples and neutron detectors. Different lithum-6 and lithium-7 isotope contents in the samples are used to measure neutron spectrum. The samples and detectors are delivered in containers to the test breeder module (TBM) on a monitor channel connecting the TBM to an operating zone of the ITER. The tritium content in the samples is measured in a laboratory by the liquid scintillation method.
Pneumatic control is used to deliver the samples to the TBM and to extract the samples using the channel during plasma-operational pauses. Neutron calculation is performed to estimate the tritium content in the samples and the heat distribution in the materials of the channel under reactor irradiation. A measurement accuracy of the tritium content in the carbonate and orthosilicate samples can attain a level of 7% and 10%, respectively. The results of the channel-cooling calculation performed under the nominal operating conditions of the TBM (a plasma pulse) are presented in the paper.</description><subject>Blanket</subject><subject>Ceramics</subject><subject>Channels</subject><subject>Design engineering</subject><subject>Dynamical systems</subject><subject>Dynamics</subject><subject>Fusion reactor</subject><subject>Lithium</subject><subject>Modules</subject><subject>Monitoring</subject><subject>Tritium</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2012</creationdate><recordtype>article</recordtype><recordid>eNqFkMFKxDAYhIMouK4-gznqoWuStklz1GXVhQVB9BzS5O-apW00SQVvvoNv6JPYdWWvwsAc_pkP_kHonJIZJZRfbWbNEKFfW4gzRiibkVGkOkATWok8E1TyQzQhkpEsF5Ifo5MYN4RQMWqCmoced753yQfXr3F6AZyCS27ocB0ALATseqxxC9p-f361Lr1sb8b7Fiw2EHTnzD56sVrNby5HoB1awL755S2fFo-n6KjRbYSzP5-i59vF0_w-Wz3cLefXq8zkRZUyXnPJWAkF03VOCklLynghGJFAcmZpWUpmhah0AbQ2ha4qwQQYkWvR1A03-RRd7Livwb8NEJPqXDTQtroHP0RFuaBFKSXhY1Tsoib4GAM06jW4TocPRYnaLqs2ar-s2i6ryChSjc3rXRPGT94dBBWNg96AdQFMUta7fxk_OUCF5g</recordid><startdate>201208</startdate><enddate>201208</enddate><creator>Kapyshev, V.</creator><creator>Kartashev, I.</creator><creator>Kovalenko, V.</creator><creator>Leshukov, A.</creator><creator>Poliksha, V.</creator><creator>Rasmerov, A.</creator><creator>Strebkov, Yu</creator><creator>Yukhnov, N.</creator><creator>Vladimirova, N.</creator><general>Elsevier B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7QQ</scope><scope>7SP</scope><scope>7TB</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>201208</creationdate><title>On monitoring the tritium breeder in a lead–lithium cooled ceramic breeder (LLCB) module of the ITER</title><author>Kapyshev, V. ; Kartashev, I. ; Kovalenko, V. ; Leshukov, A. ; Poliksha, V. ; Rasmerov, A. ; Strebkov, Yu ; Yukhnov, N. ; Vladimirova, N.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c348t-6b69225e42ab30491512647209e032d15592d778a4e1bc4a88727ec73a7fbf6c3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2012</creationdate><topic>Blanket</topic><topic>Ceramics</topic><topic>Channels</topic><topic>Design engineering</topic><topic>Dynamical systems</topic><topic>Dynamics</topic><topic>Fusion reactor</topic><topic>Lithium</topic><topic>Modules</topic><topic>Monitoring</topic><topic>Tritium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Kapyshev, V.</creatorcontrib><creatorcontrib>Kartashev, I.</creatorcontrib><creatorcontrib>Kovalenko, V.</creatorcontrib><creatorcontrib>Leshukov, A.</creatorcontrib><creatorcontrib>Poliksha, V.</creatorcontrib><creatorcontrib>Rasmerov, A.</creatorcontrib><creatorcontrib>Strebkov, Yu</creatorcontrib><creatorcontrib>Yukhnov, N.</creatorcontrib><creatorcontrib>Vladimirova, N.</creatorcontrib><collection>CrossRef</collection><collection>Ceramic Abstracts</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>Materials 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>Kapyshev, V.</au><au>Kartashev, I.</au><au>Kovalenko, V.</au><au>Leshukov, A.</au><au>Poliksha, V.</au><au>Rasmerov, A.</au><au>Strebkov, Yu</au><au>Yukhnov, N.</au><au>Vladimirova, N.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>On monitoring the tritium breeder in a lead–lithium cooled ceramic breeder (LLCB) module of the ITER</atitle><jtitle>Fusion engineering and design</jtitle><date>2012-08</date><risdate>2012</risdate><volume>87</volume><issue>5-6</issue><spage>712</spage><epage>717</epage><pages>712-717</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>The operation of a tritium breeder is a most process among engineering problems of DEMO. In this study, a design for monitoring tritium-breeding in the reactor is discussed. Additionally, a system for the experimental estimation of the tritium-breeding ratio (TBR) and the tritium-breeding dynamics in a lead–lithium cooled ceramic breeder (LLCB) test module used in the ITER is proposed. The systems are based on tritium and neutron-flux measurements under the ITER plasma D–T experiments and the use of lithium ortho-silicate and lithium carbonate samples and neutron detectors. Different lithum-6 and lithium-7 isotope contents in the samples are used to measure neutron spectrum. The samples and detectors are delivered in containers to the test breeder module (TBM) on a monitor channel connecting the TBM to an operating zone of the ITER. The tritium content in the samples is measured in a laboratory by the liquid scintillation method.
Pneumatic control is used to deliver the samples to the TBM and to extract the samples using the channel during plasma-operational pauses. Neutron calculation is performed to estimate the tritium content in the samples and the heat distribution in the materials of the channel under reactor irradiation. A measurement accuracy of the tritium content in the carbonate and orthosilicate samples can attain a level of 7% and 10%, respectively. The results of the channel-cooling calculation performed under the nominal operating conditions of the TBM (a plasma pulse) are presented in the paper.</abstract><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2012.02.008</doi><tpages>6</tpages></addata></record> |
fulltext | fulltext |
identifier | ISSN: 0920-3796 |
ispartof | Fusion engineering and design, 2012-08, Vol.87 (5-6), p.712-717 |
issn | 0920-3796 1873-7196 |
language | eng |
recordid | cdi_proquest_miscellaneous_1671459906 |
source | Elsevier ScienceDirect Journals |
subjects | Blanket Ceramics Channels Design engineering Dynamical systems Dynamics Fusion reactor Lithium Modules Monitoring Tritium |
title | On monitoring the tritium breeder in a lead–lithium cooled ceramic breeder (LLCB) module of the ITER |
url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-19T07%3A22%3A59IST&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=On%20monitoring%20the%20tritium%20breeder%20in%20a%20lead%E2%80%93lithium%20cooled%20ceramic%20breeder%20(LLCB)%20module%20of%20the%20ITER&rft.jtitle=Fusion%20engineering%20and%20design&rft.au=Kapyshev,%20V.&rft.date=2012-08&rft.volume=87&rft.issue=5-6&rft.spage=712&rft.epage=717&rft.pages=712-717&rft.issn=0920-3796&rft.eissn=1873-7196&rft_id=info:doi/10.1016/j.fusengdes.2012.02.008&rft_dat=%3Cproquest_cross%3E1671459906%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=1671459906&rft_id=info:pmid/&rft_els_id=S0920379612000634&rfr_iscdi=true |