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Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor
A 220-day irradiation of Li2TiO3 ceramics with 96% enrichment of isotope 6Li was carried out at WWRK reactor. One of the study goals was to examine tritium release behavior during Li burn-up. To achieve this goal three types of ceramics samples were examined simultaneously using a system for in-pile...
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Published in: | Journal of nuclear materials 2007-08, Vol.367-370, p.1028-1032 |
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container_title | Journal of nuclear materials |
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creator | CHIKHRAY, Y SHESTAKOV, V KULSARTOV, T TAZHIBAYEVA, I KAWAMURA, H KUYKABAEVA, A |
description | A 220-day irradiation of Li2TiO3 ceramics with 96% enrichment of isotope 6Li was carried out at WWRK reactor. One of the study goals was to examine tritium release behavior during Li burn-up. To achieve this goal three types of ceramics samples were examined simultaneously using a system for in-pile tritium monitoring: one (pebbles) - under constant temperature of 650 deg C, and two (pebbles and pellets) - within temperature change ranges from 500 to 900 deg C. Flows of tritium release from ceramics during the various reactor campaigns, as well as tritium generation rates for each ampoule are presented in the paper. The main result is justification of burn-up in 6Li reaching up to 20% of Li2TiO3 ceramics. |
doi_str_mv | 10.1016/j.jnucmat.2007.03.184 |
format | article |
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One of the study goals was to examine tritium release behavior during Li burn-up. To achieve this goal three types of ceramics samples were examined simultaneously using a system for in-pile tritium monitoring: one (pebbles) - under constant temperature of 650 deg C, and two (pebbles and pellets) - within temperature change ranges from 500 to 900 deg C. Flows of tritium release from ceramics during the various reactor campaigns, as well as tritium generation rates for each ampoule are presented in the paper. The main result is justification of burn-up in 6Li reaching up to 20% of Li2TiO3 ceramics.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2007.03.184</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. 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Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>CHIKHRAY, Y</creatorcontrib><creatorcontrib>SHESTAKOV, V</creatorcontrib><creatorcontrib>KULSARTOV, T</creatorcontrib><creatorcontrib>TAZHIBAYEVA, I</creatorcontrib><creatorcontrib>KAWAMURA, H</creatorcontrib><creatorcontrib>KUYKABAEVA, A</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Environment Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><collection>Engineered Materials Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Materials Research Database</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>Engineering Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>CHIKHRAY, Y</au><au>SHESTAKOV, V</au><au>KULSARTOV, T</au><au>TAZHIBAYEVA, I</au><au>KAWAMURA, H</au><au>KUYKABAEVA, A</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor</atitle><jtitle>Journal of nuclear materials</jtitle><date>2007-08-01</date><risdate>2007</risdate><volume>367-370</volume><spage>1028</spage><epage>1032</epage><pages>1028-1032</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>A 220-day irradiation of Li2TiO3 ceramics with 96% enrichment of isotope 6Li was carried out at WWRK reactor. One of the study goals was to examine tritium release behavior during Li burn-up. To achieve this goal three types of ceramics samples were examined simultaneously using a system for in-pile tritium monitoring: one (pebbles) - under constant temperature of 650 deg C, and two (pebbles and pellets) - within temperature change ranges from 500 to 900 deg C. Flows of tritium release from ceramics during the various reactor campaigns, as well as tritium generation rates for each ampoule are presented in the paper. The main result is justification of burn-up in 6Li reaching up to 20% of Li2TiO3 ceramics.</abstract><cop>Amsterdam</cop><pub>Elsevier</pub><doi>10.1016/j.jnucmat.2007.03.184</doi><tpages>5</tpages></addata></record> |
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subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Installations for energy generation and conversion: thermal and electrical energy |
title | Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor |
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