Summary of experimental results for ceramic breeder materials
Identifieur interne : 000139 ( France/Analysis ); précédent : 000138; suivant : 000140Summary of experimental results for ceramic breeder materials
Auteurs : N. Roux [France] ; G. Hollenberg [États-Unis] ; C. Johnson [États-Unis] ; K. Noda [Japon] ; R. Verrall [Canada]Source :
- Fusion Engineering and Design [ 0920-3796 ] ; 1995.
Abstract
Lithium-containing ceramics were quickly recognized as promising tritium breeding materials for fusion reactor blankets, particularly because of their safety advantages. Relevant material properties were investigated to evaluate further their suitability. An extensive R&D program complemented a conceptual blanket design activity either for near-term machines or for power reactors. All aspects were addressed: fabricability; overall properties (baseline, thermal, mechanical); compatibility with structures and beryllium; tritium release characteristics; irradiation behavior; activation; reprocessing; waste disposal issues. As a result of this investigation, lithium-containing ceramics are considered to be excellent tritium breeding materials.
Url:
DOI: 10.1016/0920-3796(95)90123-X
Affiliations:
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Roux</name><affiliation wicri:level="1"><country xml:lang="fr">France</country><wicri:regionArea>CEA/CE Saclay, Saclay</wicri:regionArea><wicri:noRegion>Saclay</wicri:noRegion><wicri:noRegion>Saclay</wicri:noRegion></affiliation></author><author><name sortKey="Hollenberg, G" sort="Hollenberg, G" uniqKey="Hollenberg G" first="G" last="Hollenberg">G. Hollenberg</name><affiliation wicri:level="2"><country xml:lang="fr">États-Unis</country><wicri:regionArea>Battelle, PNL, Richland, WA</wicri:regionArea><placeName><region type="state">Washington (État)</region></placeName></affiliation></author><author><name sortKey="Johnson, C" sort="Johnson, C" uniqKey="Johnson C" first="C" last="Johnson">C. Johnson</name><affiliation wicri:level="2"><country xml:lang="fr">États-Unis</country><wicri:regionArea>Argonne National Laboratory, Argonne, IL 60439</wicri:regionArea><placeName><region type="state">Illinois</region></placeName></affiliation></author><author><name sortKey="Noda, K" sort="Noda, K" uniqKey="Noda K" first="K" last="Noda">K. Noda</name><affiliation wicri:level="1"><country xml:lang="fr">Japon</country><wicri:regionArea>Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken 319-11</wicri:regionArea><wicri:noRegion>Ibaraki-ken 319-11</wicri:noRegion></affiliation></author><author><name sortKey="Verrall, R" sort="Verrall, R" uniqKey="Verrall R" first="R" last="Verrall">R. Verrall</name><affiliation wicri:level="1"><country xml:lang="fr">Canada</country><wicri:regionArea>AECL, Chalk-River, Ont.</wicri:regionArea><wicri:noRegion>Ont.</wicri:noRegion></affiliation></author></analytic><monogr></monogr><series><title level="j">Fusion Engineering and Design</title><title level="j" type="abbrev">FUSION</title><idno type="ISSN">0920-3796</idno><imprint><publisher>ELSEVIER</publisher><date type="published" when="1995">1995</date><biblScope unit="volume">27</biblScope><biblScope unit="supplement">C</biblScope><biblScope unit="page" from="154">154</biblScope><biblScope unit="page" to="166">166</biblScope></imprint><idno type="ISSN">0920-3796</idno></series><idno type="istex">0B6AB986AA6F711E6D698C2BA137F1179AEBCBAD</idno><idno type="DOI">10.1016/0920-3796(95)90123-X</idno><idno type="PII">0920-3796(95)90123-X</idno></biblStruct></sourceDesc><seriesStmt><idno type="ISSN">0920-3796</idno></seriesStmt></fileDesc><profileDesc><textClass></textClass><langUsage><language ident="en">en</language></langUsage></profileDesc></teiHeader><front><div type="abstract" xml:lang="en">Lithium-containing ceramics were quickly recognized as promising tritium breeding materials for fusion reactor blankets, particularly because of their safety advantages. Relevant material properties were investigated to evaluate further their suitability. An extensive R&D program complemented a conceptual blanket design activity either for near-term machines or for power reactors. All aspects were addressed: fabricability; overall properties (baseline, thermal, mechanical); compatibility with structures and beryllium; tritium release characteristics; irradiation behavior; activation; reprocessing; waste disposal issues. As a result of this investigation, lithium-containing ceramics are considered to be excellent tritium breeding materials.</div></front></TEI><affiliations><list><country><li>Canada</li><li>France</li><li>Japon</li><li>États-Unis</li></country><region><li>Illinois</li><li>Washington (État)</li></region></list><tree><country name="France"><noRegion><name sortKey="Roux, N" sort="Roux, N" uniqKey="Roux N" first="N" last="Roux">N. 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