Measurement of Central Void Diameter in FBR MOX Fuel by X-Ray Computer Tomography
The measurement of central void diameter in fast breeder reactor (FBR) mixed oxide fuel (MOX) was performed by using X-ray computer tomography. A pulsed high energy X-ray sources was adopted to reduce the effect of gamma-ray emission from the irradiated fuel assembly. The results showed that the art...
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Veröffentlicht in: | Journal of nuclear science and technology 2002-07, Vol.39 (7), p.804-806 |
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container_title | Journal of nuclear science and technology |
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creator | KATSUYAMA, Kozo NAGAMINE, Tsuyoshi MATSUMOTO, Shin-ichiro ITO, Masahiko |
description | The measurement of central void diameter in fast breeder reactor (FBR) mixed oxide fuel (MOX) was performed by using X-ray computer tomography. A pulsed high energy X-ray sources was adopted to reduce the effect of gamma-ray emission from the irradiated fuel assembly. The results showed that the artificial void diameter was measured with an accuracy of plus or minus 0.1 mm. |
doi_str_mv | 10.1080/18811248.2002.9715263 |
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A pulsed high energy X-ray sources was adopted to reduce the effect of gamma-ray emission from the irradiated fuel assembly. The results showed that the artificial void diameter was measured with an accuracy of plus or minus 0.1 mm.</description><identifier>ISSN: 0022-3131</identifier><identifier>EISSN: 1881-1248</identifier><identifier>DOI: 10.1080/18811248.2002.9715263</identifier><identifier>CODEN: JNSTAX</identifier><language>eng</language><publisher>Tokyo: Taylor & Francis Group</publisher><subject>Applied sciences ; central void diameter ; Computerized tomography ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fast reactors ; FBR type reactors ; Fission nuclear power plants ; Fuels ; Gamma rays ; Image processing ; Installations for energy generation and conversion: thermal and electrical energy ; Irradiation ; irradiation behavior ; Mixed oxide fuels ; MOX fuels ; Nuclear fuels ; post irradiation examination ; Preparation and processing of nuclear fuels ; Radiation effects ; Radioactive wastes ; X-ray computer tomography</subject><ispartof>Journal of nuclear science and technology, 2002-07, Vol.39 (7), p.804-806</ispartof><rights>Copyright Taylor & Francis Group, LLC 2002</rights><rights>2002 INIST-CNRS</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c4223-ee14cd2946cac3abe4375cc3c81e22253a723acd2eb6aabf9325425d18d48ea03</citedby><cites>FETCH-LOGICAL-c4223-ee14cd2946cac3abe4375cc3c81e22253a723acd2eb6aabf9325425d18d48ea03</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,776,780,27903,27904</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=13924478$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>KATSUYAMA, Kozo</creatorcontrib><creatorcontrib>NAGAMINE, Tsuyoshi</creatorcontrib><creatorcontrib>MATSUMOTO, Shin-ichiro</creatorcontrib><creatorcontrib>ITO, Masahiko</creatorcontrib><title>Measurement of Central Void Diameter in FBR MOX Fuel by X-Ray Computer Tomography</title><title>Journal of nuclear science and technology</title><description>The measurement of central void diameter in fast breeder reactor (FBR) mixed oxide fuel (MOX) was performed by using X-ray computer tomography. A pulsed high energy X-ray sources was adopted to reduce the effect of gamma-ray emission from the irradiated fuel assembly. The results showed that the artificial void diameter was measured with an accuracy of plus or minus 0.1 mm.</description><subject>Applied sciences</subject><subject>central void diameter</subject><subject>Computerized tomography</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fast reactors</subject><subject>FBR type reactors</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Gamma rays</subject><subject>Image processing</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Irradiation</subject><subject>irradiation behavior</subject><subject>Mixed oxide fuels</subject><subject>MOX fuels</subject><subject>Nuclear fuels</subject><subject>post irradiation examination</subject><subject>Preparation and processing of nuclear fuels</subject><subject>Radiation effects</subject><subject>Radioactive wastes</subject><subject>X-ray computer tomography</subject><issn>0022-3131</issn><issn>1881-1248</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2002</creationdate><recordtype>article</recordtype><recordid>eNp9kE9Lw0AQxRdRsFY_grAXvaVm_yTZ3tRqVWgpliq9LdPNRCNJtu4mSL69CW3x5mmYeb83Dx4hlywcsVCFN0wpxrhUIx6GfDROWMRjcUQG_T3ohWMy6BQeCCbYKTnz_qtbYxmrAXmdI_jGYYlVTW1GJ910UNB3m6f0IYcSa3Q0r-j0fknnizWdNljQTUvXwRJaOrHltumJlS3th4PtZ3tOTjIoPF7s55C8TR9Xk-dgtnh6mdzNAiM5FwEikyblYxkbMAI2KEUSGSOMYsg5jwQkXEBH4CYG2GRjwSPJo5SpVCqEUAzJ9e7v1tnvBn2ty9wbLAqo0DZecybjSCaiA6MdaJz13mGmty4vwbWahbovUB8K1H2Bel9g57vaB4A3UGQOKpP7P7MYcykT1XG3Oy6vMutK-LGuSHUNbWHdwST-j_oFGHeDEg</recordid><startdate>20020701</startdate><enddate>20020701</enddate><creator>KATSUYAMA, Kozo</creator><creator>NAGAMINE, Tsuyoshi</creator><creator>MATSUMOTO, Shin-ichiro</creator><creator>ITO, Masahiko</creator><general>Taylor & Francis Group</general><general>Atomic Energy Society of Japan</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope></search><sort><creationdate>20020701</creationdate><title>Measurement of Central Void Diameter in FBR MOX Fuel by X-Ray Computer Tomography</title><author>KATSUYAMA, Kozo ; NAGAMINE, Tsuyoshi ; MATSUMOTO, Shin-ichiro ; ITO, Masahiko</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c4223-ee14cd2946cac3abe4375cc3c81e22253a723acd2eb6aabf9325425d18d48ea03</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2002</creationdate><topic>Applied sciences</topic><topic>central void diameter</topic><topic>Computerized tomography</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fast reactors</topic><topic>FBR type reactors</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Gamma rays</topic><topic>Image processing</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Irradiation</topic><topic>irradiation behavior</topic><topic>Mixed oxide fuels</topic><topic>MOX fuels</topic><topic>Nuclear fuels</topic><topic>post irradiation examination</topic><topic>Preparation and processing of nuclear fuels</topic><topic>Radiation effects</topic><topic>Radioactive wastes</topic><topic>X-ray computer tomography</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>KATSUYAMA, Kozo</creatorcontrib><creatorcontrib>NAGAMINE, Tsuyoshi</creatorcontrib><creatorcontrib>MATSUMOTO, Shin-ichiro</creatorcontrib><creatorcontrib>ITO, Masahiko</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><jtitle>Journal of nuclear science and technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>KATSUYAMA, Kozo</au><au>NAGAMINE, Tsuyoshi</au><au>MATSUMOTO, Shin-ichiro</au><au>ITO, Masahiko</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Measurement of Central Void Diameter in FBR MOX Fuel by X-Ray Computer Tomography</atitle><jtitle>Journal of nuclear science and technology</jtitle><date>2002-07-01</date><risdate>2002</risdate><volume>39</volume><issue>7</issue><spage>804</spage><epage>806</epage><pages>804-806</pages><issn>0022-3131</issn><eissn>1881-1248</eissn><coden>JNSTAX</coden><abstract>The measurement of central void diameter in fast breeder reactor (FBR) mixed oxide fuel (MOX) was performed by using X-ray computer tomography. A pulsed high energy X-ray sources was adopted to reduce the effect of gamma-ray emission from the irradiated fuel assembly. The results showed that the artificial void diameter was measured with an accuracy of plus or minus 0.1 mm.</abstract><cop>Tokyo</cop><pub>Taylor & Francis Group</pub><doi>10.1080/18811248.2002.9715263</doi><tpages>3</tpages><oa>free_for_read</oa></addata></record> |
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source | Full-Text Journals in Chemistry (Open access); Alma/SFX Local Collection; EZB Electronic Journals Library |
subjects | Applied sciences central void diameter Computerized tomography Energy Energy. Thermal use of fuels Exact sciences and technology Fast reactors FBR type reactors Fission nuclear power plants Fuels Gamma rays Image processing Installations for energy generation and conversion: thermal and electrical energy Irradiation irradiation behavior Mixed oxide fuels MOX fuels Nuclear fuels post irradiation examination Preparation and processing of nuclear fuels Radiation effects Radioactive wastes X-ray computer tomography |
title | Measurement of Central Void Diameter in FBR MOX Fuel by X-Ray Computer Tomography |
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