Fabrication, properties, and tritium recovery from solid breeder materials
Identifieur interne : 000165 ( France/Analysis ); précédent : 000164; suivant : 000166Fabrication, properties, and tritium recovery from solid breeder materials
Auteurs : C. E. Johnson [États-Unis] ; T. Kondo [Japon] ; N. Roux [France] ; S. Tanaka [Japon] ; D. Vollath [Allemagne]Source :
- Fusion Engineering and Design [ 0920-3796 ] ; 1991.
Abstract
The breeding blanket is a key component of the fusion reactor because it directly involves tritium breeding and energy extraction, both of which are critical to development of fusion power. The lithium ceramics continue to show promise as candidate breeder materials. This promise was recognized by the International Thermonuclear Experimental Reactor (ITER) design team in its selection of ceramics as the first option for the ITER breeder material. Blanket design studies have indicated properties in the candidate materials data base that need further investigation. Current studies are focusing on tritium release behavior at high burn-up, changes in thermophysical properties with burn-up, compatibility between the ceramic breeder and beryllium multiplier, and phase changes with burn-up. Laboratory and in-reactor tests, some as part of an international collaboration for development of ceramic breeder materials, are underway.
Url:
DOI: 10.1016/0920-3796(91)90188-V
Affiliations:
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E." last="Johnson">C. E. Johnson</name><affiliation wicri:level="1"><country xml:lang="fr">États-Unis</country><wicri:regionArea>Argonne National Laboratory</wicri:regionArea></affiliation></author><author><name sortKey="Kondo, T" sort="Kondo, T" uniqKey="Kondo T" first="T." last="Kondo">T. Kondo</name><affiliation wicri:level="1"><country xml:lang="fr">Japon</country><wicri:regionArea>Japan Atomic Energy Research Institute</wicri:regionArea></affiliation></author><author><name sortKey="Roux, N" sort="Roux, N" uniqKey="Roux N" first="N." last="Roux">N. Roux</name><affiliation wicri:level="1"><country xml:lang="fr">France</country><wicri:regionArea>Commissariat à l'Énergie Atomique</wicri:regionArea></affiliation></author><author><name sortKey="Tanaka, S" sort="Tanaka, S" uniqKey="Tanaka S" first="S." last="Tanaka">S. Tanaka</name><affiliation wicri:level="1"><country xml:lang="fr">Japon</country><wicri:regionArea>University of Tokyo</wicri:regionArea></affiliation></author><author><name sortKey="Vollath, D" sort="Vollath, D" uniqKey="Vollath D" first="D." last="Vollath">D. Vollath</name><affiliation wicri:level="1"><country xml:lang="fr">Allemagne</country><wicri:regionArea>Kernforschungszentrum Karlsruhe</wicri:regionArea></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="1991">1991</date><biblScope unit="volume">16</biblScope><biblScope unit="supplement">C</biblScope><biblScope unit="page" from="127">127</biblScope><biblScope unit="page" to="139">139</biblScope></imprint><idno type="ISSN">0920-3796</idno></series><idno type="istex">FBE4E67BFCB1F93D939B4F82D2E4F8A096DC61A0</idno><idno type="DOI">10.1016/0920-3796(91)90188-V</idno><idno type="PII">0920-3796(91)90188-V</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">The breeding blanket is a key component of the fusion reactor because it directly involves tritium breeding and energy extraction, both of which are critical to development of fusion power. The lithium ceramics continue to show promise as candidate breeder materials. This promise was recognized by the International Thermonuclear Experimental Reactor (ITER) design team in its selection of ceramics as the first option for the ITER breeder material. Blanket design studies have indicated properties in the candidate materials data base that need further investigation. Current studies are focusing on tritium release behavior at high burn-up, changes in thermophysical properties with burn-up, compatibility between the ceramic breeder and beryllium multiplier, and phase changes with burn-up. Laboratory and in-reactor tests, some as part of an international collaboration for development of ceramic breeder materials, are underway.</div></front></TEI><affiliations><list><country><li>Allemagne</li><li>France</li><li>Japon</li><li>États-Unis</li></country></list><tree><country name="États-Unis"><noRegion><name sortKey="Johnson, C E" sort="Johnson, C E" uniqKey="Johnson C" first="C. E." last="Johnson">C. E. Johnson</name></noRegion></country><country name="Japon"><noRegion><name sortKey="Kondo, T" sort="Kondo, T" uniqKey="Kondo T" first="T." last="Kondo">T. Kondo</name></noRegion><name sortKey="Tanaka, S" sort="Tanaka, S" uniqKey="Tanaka S" first="S." last="Tanaka">S. Tanaka</name></country><country name="France"><noRegion><name sortKey="Roux, N" sort="Roux, N" uniqKey="Roux N" first="N." last="Roux">N. Roux</name></noRegion></country><country name="Allemagne"><noRegion><name sortKey="Vollath, D" sort="Vollath, D" uniqKey="Vollath D" first="D." last="Vollath">D. Vollath</name></noRegion></country></tree></affiliations></record>Pour manipuler ce document sous Unix (Dilib)
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