Opportunities for Advanced Ceramics and Composites in the Nuclear Sector
Identifieur interne : 001A38 ( Istex/Corpus ); précédent : 001A37; suivant : 001A39Opportunities for Advanced Ceramics and Composites in the Nuclear Sector
Auteurs : William Edward Lee ; Matthew Gilbert ; Samuel Thomas Murphy ; Robin William GrimesSource :
- Journal of the American Ceramic Society [ 0002-7820 ] ; 2013-07.
Abstract
Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (ILW) and also for oxide nuclear fuels based on UO2 and PuO2/UO2 mixed oxides. They are also used as porous filters with the ability to absorb radionuclides (RN) from air and liquids and are playing a key role in the cleanup at Fukushima. Non‐oxides also find current fission applications including in graphite moderators and B4C control rods. Ceramics will continue to be significant in the near‐term expansion of nuclear power via next‐step developments of fuels with inert matrices or based on thoria and in wasteforms using alternative composite cements or single or multiphase ceramics that can host Pu & other difficult RN. Longer term advances for Generation IV reactors, which will operate at higher temperatures & with higher fuel burn‐up require innovative fuel developments potentially via carbides & nitrides or composite fuel systems. Novel non‐thermal (cement‐like) and thermal techniques are currently being developed to treat some of the difficult legacy wastes. Non‐thermally derived wasteforms developed from geopolymers, composite cements, hydroceramics, and phosphate‐bonded ceramics and thermally derived wasteforms made by Hot Isostatic Pressing and fluidized bed steam reforming (FBSR) as well as vitrification techniques based on cold crucible melting (CCM), Joule‐heater in‐container melting and plasma melting (PM) are described. Future developments in waste treatment will be based on separation technologies for partitioning individual RN along with design & construction of RN‐containing ceramic targets for inducing transmutation reactions. Near demonstration actinide‐hosting ceramic wasteforms including multiphase Synroc systems are described. Opportunities also exist for ceramics in structural applications in Generation IV reactors such as composite SiC/SiC and C/C for fuel cladding and control rods and MAX phases and ultrahigh‐temperature ceramics (UHTCs) may find near core fuel coating and cladding applications. Uses of ceramics in fusion reactor systems will be both functional (ceramic superconductors in magnet systems for plasma control and in Li silicate breeder blankets in tokamaks) and structural including as sapphire diagnostic windows, graphite diverters, and plasma facing C and UHTCs. In all these cases, performance is limited by poorly understood radiation damage and interface controlled processes, which demands a combined modeling/experimental approach.
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DOI: 10.1111/jace.12406
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<record><TEI wicri:istexFullTextTei="biblStruct"><teiHeader><fileDesc><titleStmt><title xml:lang="en">Opportunities for Advanced Ceramics and Composites in the Nuclear Sector</title><author><name sortKey="Lee, William Edward" sort="Lee, William Edward" uniqKey="Lee W" first="William Edward" last="Lee">William Edward Lee</name><affiliation><mods:affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</mods:affiliation></affiliation></author><author><name sortKey="Gilbert, Matthew" sort="Gilbert, Matthew" uniqKey="Gilbert M" first="Matthew" last="Gilbert">Matthew Gilbert</name><affiliation><mods:affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</mods:affiliation></affiliation></author><author><name sortKey="Murphy, Samuel Thomas" sort="Murphy, Samuel Thomas" uniqKey="Murphy S" first="Samuel Thomas" last="Murphy">Samuel Thomas Murphy</name><affiliation><mods:affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</mods:affiliation></affiliation></author><author><name sortKey="Grimes, Robin William" sort="Grimes, Robin William" uniqKey="Grimes R" first="Robin William" last="Grimes">Robin William Grimes</name><affiliation><mods:affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</mods:affiliation></affiliation></author></titleStmt><publicationStmt><idno type="wicri:source">ISTEX</idno><idno type="RBID">ISTEX:08CEA47A72A9186DA2FB9B410FC261F25A9B3F17</idno><date when="2013" year="2013">2013</date><idno type="doi">10.1111/jace.12406</idno><idno type="url">https://api.istex.fr/document/08CEA47A72A9186DA2FB9B410FC261F25A9B3F17/fulltext/pdf</idno><idno type="wicri:Area/Istex/Corpus">001A38</idno></publicationStmt><sourceDesc><biblStruct><analytic><title level="a" type="main" xml:lang="en">Opportunities for Advanced Ceramics and Composites in the Nuclear Sector</title><author><name sortKey="Lee, William Edward" sort="Lee, William Edward" uniqKey="Lee W" first="William Edward" last="Lee">William Edward Lee</name><affiliation><mods:affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</mods:affiliation></affiliation></author><author><name sortKey="Gilbert, Matthew" sort="Gilbert, Matthew" uniqKey="Gilbert M" first="Matthew" last="Gilbert">Matthew Gilbert</name><affiliation><mods:affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</mods:affiliation></affiliation></author><author><name sortKey="Murphy, Samuel Thomas" sort="Murphy, Samuel Thomas" uniqKey="Murphy S" first="Samuel Thomas" last="Murphy">Samuel Thomas Murphy</name><affiliation><mods:affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</mods:affiliation></affiliation></author><author><name sortKey="Grimes, Robin William" sort="Grimes, Robin William" uniqKey="Grimes R" first="Robin William" last="Grimes">Robin William Grimes</name><affiliation><mods:affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</mods:affiliation></affiliation></author></analytic><monogr></monogr><series><title level="j">Journal of the American Ceramic Society</title><title level="j" type="abbrev">J. Am. Ceram. Soc.</title><idno type="ISSN">0002-7820</idno><idno type="eISSN">1551-2916</idno><imprint><publisher>Blackwell Publishing Ltd</publisher><date type="published" when="2013-07">2013-07</date><biblScope unit="volume">96</biblScope><biblScope unit="issue">7</biblScope><biblScope unit="page" from="2005">2005</biblScope><biblScope unit="page" to="2030">2030</biblScope></imprint><idno type="ISSN">0002-7820</idno></series><idno type="istex">08CEA47A72A9186DA2FB9B410FC261F25A9B3F17</idno><idno type="DOI">10.1111/jace.12406</idno><idno type="ArticleID">JACE12406</idno></biblStruct></sourceDesc><seriesStmt><idno type="ISSN">0002-7820</idno></seriesStmt></fileDesc><profileDesc><textClass></textClass><langUsage><language ident="en">en</language></langUsage></profileDesc></teiHeader><front><div type="abstract">Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (ILW) and also for oxide nuclear fuels based on UO2 and PuO2/UO2 mixed oxides. They are also used as porous filters with the ability to absorb radionuclides (RN) from air and liquids and are playing a key role in the cleanup at Fukushima. Non‐oxides also find current fission applications including in graphite moderators and B4C control rods. Ceramics will continue to be significant in the near‐term expansion of nuclear power via next‐step developments of fuels with inert matrices or based on thoria and in wasteforms using alternative composite cements or single or multiphase ceramics that can host Pu & other difficult RN. Longer term advances for Generation IV reactors, which will operate at higher temperatures & with higher fuel burn‐up require innovative fuel developments potentially via carbides & nitrides or composite fuel systems. Novel non‐thermal (cement‐like) and thermal techniques are currently being developed to treat some of the difficult legacy wastes. Non‐thermally derived wasteforms developed from geopolymers, composite cements, hydroceramics, and phosphate‐bonded ceramics and thermally derived wasteforms made by Hot Isostatic Pressing and fluidized bed steam reforming (FBSR) as well as vitrification techniques based on cold crucible melting (CCM), Joule‐heater in‐container melting and plasma melting (PM) are described. Future developments in waste treatment will be based on separation technologies for partitioning individual RN along with design & construction of RN‐containing ceramic targets for inducing transmutation reactions. Near demonstration actinide‐hosting ceramic wasteforms including multiphase Synroc systems are described. Opportunities also exist for ceramics in structural applications in Generation IV reactors such as composite SiC/SiC and C/C for fuel cladding and control rods and MAX phases and ultrahigh‐temperature ceramics (UHTCs) may find near core fuel coating and cladding applications. Uses of ceramics in fusion reactor systems will be both functional (ceramic superconductors in magnet systems for plasma control and in Li silicate breeder blankets in tokamaks) and structural including as sapphire diagnostic windows, graphite diverters, and plasma facing C and UHTCs. In all these cases, performance is limited by poorly understood radiation damage and interface controlled processes, which demands a combined modeling/experimental approach.</div></front></TEI><istex><corpusName>wiley</corpusName><editor><json:item><name>D. J. Green</name></json:item></editor><author><json:item><name>William Edward Lee</name><affiliations><json:string>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</json:string></affiliations></json:item><json:item><name>Matthew Gilbert</name><affiliations><json:string>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</json:string></affiliations></json:item><json:item><name>Samuel Thomas Murphy</name><affiliations><json:string>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</json:string></affiliations></json:item><json:item><name>Robin William Grimes</name><affiliations><json:string>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</json:string></affiliations></json:item></author><articleId><json:string>JACE12406</json:string></articleId><language><json:string>eng</json:string></language><originalGenre><json:string>article</json:string></originalGenre><abstract>Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (ILW) and also for oxide nuclear fuels based on UO2 and PuO2/UO2 mixed oxides. They are also used as porous filters with the ability to absorb radionuclides (RN) from air and liquids and are playing a key role in the cleanup at Fukushima. Non‐oxides also find current fission applications including in graphite moderators and B4C control rods. Ceramics will continue to be significant in the near‐term expansion of nuclear power via next‐step developments of fuels with inert matrices or based on thoria and in wasteforms using alternative composite cements or single or multiphase ceramics that can host Pu & other difficult RN. Longer term advances for Generation IV reactors, which will operate at higher temperatures & with higher fuel burn‐up require innovative fuel developments potentially via carbides & nitrides or composite fuel systems. Novel non‐thermal (cement‐like) and thermal techniques are currently being developed to treat some of the difficult legacy wastes. Non‐thermally derived wasteforms developed from geopolymers, composite cements, hydroceramics, and phosphate‐bonded ceramics and thermally derived wasteforms made by Hot Isostatic Pressing and fluidized bed steam reforming (FBSR) as well as vitrification techniques based on cold crucible melting (CCM), Joule‐heater in‐container melting and plasma melting (PM) are described. Future developments in waste treatment will be based on separation technologies for partitioning individual RN along with design & construction of RN‐containing ceramic targets for inducing transmutation reactions. Near demonstration actinide‐hosting ceramic wasteforms including multiphase Synroc systems are described. Opportunities also exist for ceramics in structural applications in Generation IV reactors such as composite SiC/SiC and C/C for fuel cladding and control rods and MAX phases and ultrahigh‐temperature ceramics (UHTCs) may find near core fuel coating and cladding applications. Uses of ceramics in fusion reactor systems will be both functional (ceramic superconductors in magnet systems for plasma control and in Li silicate breeder blankets in tokamaks) and structural including as sapphire diagnostic windows, graphite diverters, and plasma facing C and UHTCs. 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J.</forename><surname>Green</surname></persName></editor></analytic><monogr><title level="j">Journal of the American Ceramic Society</title><title level="j" type="abbrev">J. Am. Ceram. Soc.</title><idno type="pISSN">0002-7820</idno><idno type="eISSN">1551-2916</idno><idno type="DOI">10.1111/(ISSN)1551-2916</idno><imprint><publisher>Blackwell Publishing Ltd</publisher><date type="published" when="2013-07"></date><biblScope unit="volume">96</biblScope><biblScope unit="issue">7</biblScope><biblScope unit="page" from="2005">2005</biblScope><biblScope unit="page" to="2030">2030</biblScope></imprint></monogr><idno type="istex">08CEA47A72A9186DA2FB9B410FC261F25A9B3F17</idno><idno type="DOI">10.1111/jace.12406</idno><idno type="ArticleID">JACE12406</idno></biblStruct></sourceDesc></fileDesc><profileDesc><creation><date>2013-05-15</date></creation><langUsage><language ident="en">en</language></langUsage><abstract><p>Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (ILW) and also for oxide nuclear fuels based on UO2 and PuO2/UO2 mixed oxides. They are also used as porous filters with the ability to absorb radionuclides (RN) from air and liquids and are playing a key role in the cleanup at Fukushima. Non‐oxides also find current fission applications including in graphite moderators and B4C control rods. Ceramics will continue to be significant in the near‐term expansion of nuclear power via next‐step developments of fuels with inert matrices or based on thoria and in wasteforms using alternative composite cements or single or multiphase ceramics that can host Pu & other difficult RN. Longer term advances for Generation IV reactors, which will operate at higher temperatures & with higher fuel burn‐up require innovative fuel developments potentially via carbides & nitrides or composite fuel systems. Novel non‐thermal (cement‐like) and thermal techniques are currently being developed to treat some of the difficult legacy wastes. Non‐thermally derived wasteforms developed from geopolymers, composite cements, hydroceramics, and phosphate‐bonded ceramics and thermally derived wasteforms made by Hot Isostatic Pressing and fluidized bed steam reforming (FBSR) as well as vitrification techniques based on cold crucible melting (CCM), Joule‐heater in‐container melting and plasma melting (PM) are described. Future developments in waste treatment will be based on separation technologies for partitioning individual RN along with design & construction of RN‐containing ceramic targets for inducing transmutation reactions. Near demonstration actinide‐hosting ceramic wasteforms including multiphase Synroc systems are described. Opportunities also exist for ceramics in structural applications in Generation IV reactors such as composite SiC/SiC and C/C for fuel cladding and control rods and MAX phases and ultrahigh‐temperature ceramics (UHTCs) may find near core fuel coating and cladding applications. Uses of ceramics in fusion reactor systems will be both functional (ceramic superconductors in magnet systems for plasma control and in Li silicate breeder blankets in tokamaks) and structural including as sapphire diagnostic windows, graphite diverters, and plasma facing C and UHTCs. In all these cases, performance is limited by poorly understood radiation damage and interface controlled processes, which demands a combined modeling/experimental approach.</p></abstract><textClass><keywords scheme="Journal Subject"><list><head>article-category</head><item><term>Feature Article</term></item></list></keywords></textClass></profileDesc><revisionDesc><change when="2013-01-29">Received</change><change when="2013-04-23">Registration</change><change when="2013-05-15">Created</change><change when="2013-07">Published</change></revisionDesc></teiHeader></istex:fulltextTEI><json:item><original>false</original><mimetype>text/plain</mimetype><extension>txt</extension><uri>https://api.istex.fr/document/08CEA47A72A9186DA2FB9B410FC261F25A9B3F17/fulltext/txt</uri></json:item></fulltext><metadata><istex:metadataXml wicri:clean="Wiley, elements deleted: body"><istex:xmlDeclaration>version="1.0" encoding="UTF-8" standalone="yes"</istex:xmlDeclaration><istex:document><component type="serialArticle" version="2.0" xml:id="jace12406" xml:lang="en"><header><publicationMeta level="product"><doi origin="wiley" registered="yes">10.1111/(ISSN)1551-2916</doi><issn type="print">0002-7820</issn><issn type="electronic">1551-2916</issn><idGroup><id type="product" value="JACE"></id></idGroup><titleGroup><title sort="JOURNAL OF THE AMERICAN CERAMIC SOCIETY" type="main">Journal of the American Ceramic Society</title><title type="short">J. 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Soc.</title></titleGroup></publicationMeta><publicationMeta level="part" position="70"><doi origin="wiley">10.1111/jace.2013.96.issue-7</doi><copyright ownership="thirdParty">© 2013 American Ceramic Society</copyright><numberingGroup><numbering type="journalVolume" number="96">96</numbering><numbering type="journalIssue">7</numbering></numberingGroup><coverDate startDate="2013-07">July 2013</coverDate></publicationMeta><publicationMeta level="unit" position="10" status="forIssue" type="article"><doi>10.1111/jace.12406</doi><idGroup><id type="unit" value="JACE12406"></id></idGroup><countGroup><count number="26" type="pageTotal"></count></countGroup><titleGroup><title type="articleCategory">Feature Article</title><title type="tocHeading1">Feature</title></titleGroup><copyright ownership="thirdParty">© 2013 The American Ceramic Society</copyright><eventGroup><event date="2013-01-29" type="manuscriptReceived"></event><event date="2013-04-23" type="manuscriptAccepted"></event><event agent="SPS" date="2013-05-15" type="xmlCreated"></event><event type="publishedOnlineEarlyUnpaginated" date="2013-06-11"></event><event type="publishedOnlineFinalForm" date="2013-07-12"></event><event type="firstOnline" date="2013-06-11"></event><event type="xmlConverted" agent="Converter:WILEY_ML3G_TO_WILEY_ML3GV2 version:4.0.1" date="2014-03-19"></event><event type="xmlConverted" agent="Converter:WML3G_To_WML3G version:4.6.4 mode:FullText" date="2015-10-02"></event></eventGroup><numberingGroup><numbering type="pageFirst">2005</numbering><numbering type="pageLast">2030</numbering></numberingGroup><correspondenceTo>Author to whom correspondence should be addressed. e‐mail: <email>w.e.lee@imperial.ac.uk</email></correspondenceTo><linkGroup><link type="toTypesetVersion" href="file:JACE.JACE12406.pdf"></link></linkGroup></publicationMeta><contentMeta><titleGroup><title type="main">Opportunities for Advanced Ceramics and Composites in the Nuclear Sector</title><title type="shortAuthors">Lee et al.</title></titleGroup><creators><creator affiliationRef="#jace12406-aff-0001" noteRef="#jace12406-note-0002" corresponding="yes" creatorRole="author" xml:id="jace12406-cr-0001"><personName><givenNames>William Edward</givenNames> <familyName>Lee</familyName></personName><biographyInfo xml:id="jace12406-biog-0001"><p>Prof. Bill Lee was head of the Materials Department at Imperial College from 2006 to 2008 after 17 yr at the University of Sheffield. He spent 6 yr in the USA in the 1980s at Case Western Reserve and Ohio State Universities. He has studied microstructure‐processing—property relations in refractories, glass ceramics, electroceramics and, more recently, in nuclear fuels/wasteforms and ultra‐high temperature ceramics (UHTCs). He is currently Director of the Centre for Nuclear Engineering at Imperial College, Deputy Chair of the UK Government advisory Committee on Radioactive Waste Management (CoRWM) and an AWE William Penney Fellow. He was made a Fellow of the Royal Academy of Engineering in 2012.</p><mediaResourceGroup><mediaResource alt="image" href="urn:x-wiley:00027820:media:jace12406:jace12406-fig-0025"></mediaResource></mediaResourceGroup></biographyInfo></creator><creator affiliationRef="#jace12406-aff-0001" creatorRole="author" xml:id="jace12406-cr-0002"><personName><givenNames>Matthew</givenNames> <familyName>Gilbert</familyName></personName><biographyInfo xml:id="jace12406-biog-0004"><p>Dr. Matthew Gilbert is currently an Inorganic Materials Scientist as part of ceramics and glass research at AWE, Aldermarston UK. His research interests include the development of ceramic and glass‐ceramic phases for the immobilisation of separated actinides and high level wastes, the effects of radiation damage in ceramics and the durability and ageing mechanisms of ceramic and glass materials. Currently, his work is focussed on the fabrication of ceramic materials for the immobilisation of halide‐rich wastes, such as those resulting from pyrochemical reprocessing operations.</p><mediaResourceGroup><mediaResource alt="image" href="urn:x-wiley:00027820:media:jace12406:jace12406-fig-0026"></mediaResource></mediaResourceGroup></biographyInfo></creator><creator affiliationRef="#jace12406-aff-0001" creatorRole="author" xml:id="jace12406-cr-0003"><personName><givenNames>Samuel Thomas</givenNames> <familyName>Murphy</familyName></personName><biographyInfo xml:id="jace12406-biog-0003"><p>Dr. Samuel Murphy is a Research Associate in the Centre of Nuclear Engineering at Imperial College London. His research interests include computer simulation to study fundamental processes occurring on the atomic scale in nuclear materials, including point and extended defect formation resulting from the interaction with radiation. Currently, his work is focussed on UO<sub>2</sub> and mixed oxide fuels and the interaction of the fuel with the Zr cladding as well as Li ceramic materials for use in fusion reactors.</p><mediaResourceGroup><mediaResource alt="image" href="urn:x-wiley:00027820:media:jace12406:jace12406-fig-0027"></mediaResource></mediaResourceGroup></biographyInfo></creator><creator affiliationRef="#jace12406-aff-0001" noteRef="#jace12406-note-0002" creatorRole="author" xml:id="jace12406-cr-0004"><personName><givenNames>Robin William</givenNames> <familyName>Grimes</familyName></personName><biographyInfo xml:id="jace12406-biog-0002"><p>Prof. Robin Grimes joined the Materials Department at Imperial College in 1995 and was appointed Professor of Materials Physics in 2002. He spent the year 2000 at Los Alamos National Laboratory as Bernd T. Matthias Scholar. His research focuses on the application and development of computer simulation techniques to predict structural and dynamic properties of inorganic materials for energy applications, to improve performance of semiconductors for solar and electrolytes and electrodes for fuel cells, nuclear fuel for higher burn‐up and waste forms of greater durability. He has published over 240 scientific papers. In 2013 he was appointed Chief Scientific Advisor to the UK's Foreign and Commonwealth Office.</p><mediaResourceGroup><mediaResource alt="image" href="urn:x-wiley:00027820:media:jace12406:jace12406-fig-0028"></mediaResource></mediaResourceGroup></biographyInfo></creator><creator creatorRole="editor" xml:id="jace12406-cr-0005"><personName><givenNames>D. J.</givenNames> <familyName>Green</familyName></personName></creator></creators><affiliationGroup><affiliation countryCode="GB" type="organization" xml:id="jace12406-aff-0001"><orgDiv>Centre for Nuclear Engineering, and Department of Materials</orgDiv> <orgName>Imperial College London</orgName> <address><postCode>SW7 2AZ</postCode> <country>UK</country></address></affiliation></affiliationGroup><abstractGroup><abstract type="main" xml:id="jace12406-abs-0001"><p>Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (<fc>ILW</fc>) and also for oxide nuclear fuels based on <fc>UO</fc><sub>2</sub> and <fc><fr>PuO</fr></fc><sub>2</sub>/<fc>UO</fc><sub>2</sub> mixed oxides. They are also used as porous filters with the ability to absorb radionuclides (<fc>RN</fc>) from air and liquids and are playing a key role in the cleanup at Fukushima. Non‐oxides also find current fission applications including in graphite moderators and <fc><fr>B</fr></fc><sub>4</sub><fc><fr>C</fr></fc> control rods. Ceramics will continue to be significant in the near‐term expansion of nuclear power via next‐step developments of fuels with inert matrices or based on thoria and in wasteforms using alternative composite cements or single or multiphase ceramics that can host Pu & other difficult <fc>RN</fc>. Longer term advances for Generation <fc>IV</fc> reactors, which will operate at higher temperatures & with higher fuel burn‐up require innovative fuel developments potentially via carbides & nitrides or composite fuel systems. Novel non‐thermal (cement‐like) and thermal techniques are currently being developed to treat some of the difficult legacy wastes. Non‐thermally derived wasteforms developed from geopolymers, composite cements, hydroceramics, and phosphate‐bonded ceramics and thermally derived wasteforms made by Hot Isostatic Pressing and fluidized bed steam reforming (<fc>FBSR</fc>) as well as vitrification techniques based on cold crucible melting (<fc>CCM</fc>), Joule‐heater in‐container melting and plasma melting (<fc>PM</fc>) are described. Future developments in waste treatment will be based on separation technologies for partitioning individual <fc>RN</fc> along with design & construction of <fc>RN</fc>‐containing ceramic targets for inducing transmutation reactions. Near demonstration actinide‐hosting ceramic wasteforms including multiphase Synroc systems are described. Opportunities also exist for ceramics in structural applications in Generation <fc>IV</fc> reactors such as composite <fc><fr>SiC</fr></fc>/<fc><fr>SiC</fr></fc> and <fc><fr>C</fr></fc>/<fc><fr>C</fr></fc> for fuel cladding and control rods and <fc>MAX</fc> phases and ultrahigh‐temperature ceramics (<fc>UHTC</fc>s) may find near core fuel coating and cladding applications. Uses of ceramics in fusion reactor systems will be both functional (ceramic superconductors in magnet systems for plasma control and in Li silicate breeder blankets in tokamaks) and structural including as sapphire diagnostic windows, graphite diverters, and plasma facing <fc><fr>C</fr></fc> and <fc>UHTC</fc>s. In all these cases, performance is limited by poorly understood radiation damage and interface controlled processes, which demands a combined modeling/experimental approach.</p></abstract></abstractGroup></contentMeta><noteGroup xml:id="jace12406-ntgp-0001"><note numbered="no" xml:id="jace12406-note-0001">Based on a plenary lecture presented at the ICACC, Daytona Beach, FL, USA, January 2011.</note><note xml:id="jace12406-note-0002">Fellow, The American Ceramic Society.</note></noteGroup></header></component></istex:document></istex:metadataXml><mods version="3.6"><titleInfo lang="en"><title>Opportunities for Advanced Ceramics and Composites in the Nuclear Sector</title></titleInfo><titleInfo type="alternative" contentType="CDATA" lang="en"><title>Opportunities for Advanced Ceramics and Composites in the Nuclear Sector</title></titleInfo><name type="personal"><namePart type="given">William Edward</namePart><namePart type="family">Lee</namePart><affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</affiliation><description>Fellow, The American Ceramic Society.</description><description>Correspondence: Author to whom correspondence should be addressed. e‐mail: </description><role><roleTerm type="text">author</roleTerm></role></name><name type="personal"><namePart type="given">Matthew</namePart><namePart type="family">Gilbert</namePart><affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</affiliation><role><roleTerm type="text">author</roleTerm></role></name><name type="personal"><namePart type="given">Samuel Thomas</namePart><namePart type="family">Murphy</namePart><affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</affiliation><role><roleTerm type="text">author</roleTerm></role></name><name type="personal"><namePart type="given">Robin William</namePart><namePart type="family">Grimes</namePart><affiliation>Centre for Nuclear Engineering, and Department of Materials, Imperial College London, SW7 2AZ, UK</affiliation><description>Fellow, The American Ceramic Society.</description><role><roleTerm type="text">author</roleTerm></role></name><name type="personal"><namePart type="given">D. J.</namePart><namePart type="family">Green</namePart><role><roleTerm type="text">editor</roleTerm></role></name><typeOfResource>text</typeOfResource><genre type="article" displayLabel="article"></genre><originInfo><publisher>Blackwell Publishing Ltd</publisher><dateIssued encoding="w3cdtf">2013-07</dateIssued><dateCreated encoding="w3cdtf">2013-05-15</dateCreated><dateCaptured encoding="w3cdtf">2013-01-29</dateCaptured><dateValid encoding="w3cdtf">2013-04-23</dateValid><copyrightDate encoding="w3cdtf">2013</copyrightDate></originInfo><language><languageTerm type="code" authority="rfc3066">en</languageTerm><languageTerm type="code" authority="iso639-2b">eng</languageTerm></language><physicalDescription><internetMediaType>text/html</internetMediaType></physicalDescription><abstract>Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (ILW) and also for oxide nuclear fuels based on UO2 and PuO2/UO2 mixed oxides. They are also used as porous filters with the ability to absorb radionuclides (RN) from air and liquids and are playing a key role in the cleanup at Fukushima. Non‐oxides also find current fission applications including in graphite moderators and B4C control rods. Ceramics will continue to be significant in the near‐term expansion of nuclear power via next‐step developments of fuels with inert matrices or based on thoria and in wasteforms using alternative composite cements or single or multiphase ceramics that can host Pu & other difficult RN. Longer term advances for Generation IV reactors, which will operate at higher temperatures & with higher fuel burn‐up require innovative fuel developments potentially via carbides & nitrides or composite fuel systems. Novel non‐thermal (cement‐like) and thermal techniques are currently being developed to treat some of the difficult legacy wastes. Non‐thermally derived wasteforms developed from geopolymers, composite cements, hydroceramics, and phosphate‐bonded ceramics and thermally derived wasteforms made by Hot Isostatic Pressing and fluidized bed steam reforming (FBSR) as well as vitrification techniques based on cold crucible melting (CCM), Joule‐heater in‐container melting and plasma melting (PM) are described. Future developments in waste treatment will be based on separation technologies for partitioning individual RN along with design & construction of RN‐containing ceramic targets for inducing transmutation reactions. Near demonstration actinide‐hosting ceramic wasteforms including multiphase Synroc systems are described. Opportunities also exist for ceramics in structural applications in Generation IV reactors such as composite SiC/SiC and C/C for fuel cladding and control rods and MAX phases and ultrahigh‐temperature ceramics (UHTCs) may find near core fuel coating and cladding applications. Uses of ceramics in fusion reactor systems will be both functional (ceramic superconductors in magnet systems for plasma control and in Li silicate breeder blankets in tokamaks) and structural including as sapphire diagnostic windows, graphite diverters, and plasma facing C and UHTCs. In all these cases, performance is limited by poorly understood radiation damage and interface controlled processes, which demands a combined modeling/experimental approach.</abstract><relatedItem type="host"><titleInfo><title>Journal of the American Ceramic Society</title></titleInfo><titleInfo type="abbreviated"><title>J. Am. Ceram. Soc.</title></titleInfo><genre type="journal">journal</genre><subject><genre>article-category</genre><topic>Feature Article</topic></subject><identifier type="ISSN">0002-7820</identifier><identifier type="eISSN">1551-2916</identifier><identifier type="DOI">10.1111/(ISSN)1551-2916</identifier><identifier type="PublisherID">JACE</identifier><part><date>2013</date><detail type="volume"><caption>vol.</caption><number>96</number></detail><detail type="issue"><caption>no.</caption><number>7</number></detail><extent unit="pages"><start>2005</start><end>2030</end><total>26</total></extent></part></relatedItem><identifier type="istex">08CEA47A72A9186DA2FB9B410FC261F25A9B3F17</identifier><identifier type="DOI">10.1111/jace.12406</identifier><identifier type="ArticleID">JACE12406</identifier><accessCondition type="use and reproduction" contentType="copyright">© 2013 American Ceramic Society© 2013 The American Ceramic Society</accessCondition><recordInfo><recordContentSource>WILEY</recordContentSource></recordInfo></mods></metadata><enrichments><json:item><type>multicat</type><uri>https://api.istex.fr/document/08CEA47A72A9186DA2FB9B410FC261F25A9B3F17/enrichments/multicat</uri></json:item></enrichments><serie></serie></istex></record>Pour manipuler ce document sous Unix (Dilib)
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