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Titre du document / Document title

Ti-doped isotropic graphite: A promising armour material for plasma-facing components

Auteur(s) / Author(s)

GARCIA-ROSALES C. (1) ; LOPEZ-GALILEA I. (1) ; ORDAS N. (1) ; ADELHELM C. (2) ; BALDEN M. (2) ; PINTSUK G. (3) ; GRATTAROLA M. (4) ; GUALCO C. (4) ;

Affiliation(s) du ou des auteurs / Author(s) Affiliation(s)

(1) CEIT and Tecnun (University of Navarra), Paseo de Manuel Lardizabal, 15, 20018 San Sebastián, ESPAGNE
(2) Max-Planck-Institut für Plasmaphysik, EURATOM Association, 85748 Garching, ALLEMAGNE
(3) Forschungszentrum Jülich GmbH, EURATOM Association, 52425 Jülich, ALLEMAGNE
(4) Ansaldo Ricerche S.p.A., 16152 Genoa, ITALIE

Résumé / Abstract

Finely dispersed Ti-doped isotropic graphites with 4 at.% Ti have been manufactured using synthetic mesophase pitch 'AR' as raw material. These new materials show a thermal conductivity at room temperature of ∼200 W/mK and flexural strength close to 100 MPa. Measurement of the total erosion yield by deuterium bombardment at ion energies and sample temperatures for which pure carbon shows maximum values, resulted in a reduction of at least a factor of 4, mainly due to dopant enrichment at the surface caused by preferential erosion of carbon. In addition, ITER relevant thermal shock loads were applied with an energetic electron beam at the JUDITH facility. The results demonstrated a significantly improved performance of Ti-doped graphite compared to pure graphite. Finally, Ti-doped graphite was successfully brazed to a CuCrZr block using a Mo interlayer. These results let assume that Ti-doped graphite can be a promising armour material for divertor plasma-facing components.

Revue / Journal Title

Journal of nuclear materials    ISSN  0022-3115   CODEN JNUMAM 

Source / Source

Congrès
International Conference on Fusion Reactor Materials (ICFRM) No13, Nice , FRANCE (10/12/2007)
2009, vol. 386-88 (1120 p.)  [Document : 4 p.] (17 ref.), pp. 801-804 [4 page(s) (article)]

Langue / Language

Anglais

Editeur / Publisher

Elsevier, Amsterdam, PAYS-BAS  (1959) (Revue)

Mots-clés anglais / English Keywords

Nuclear reactor

;

Divertor

;

Molybdenum

;

Electron beam

;

Tokamak

;

Carbon

;

Deuterium

;

Erosion

;

Strength

;

Thermal conductivity

;

Nuclear fusion reactor

;

Surface plasma interaction

;

Graphite

;

Isotropic material

;

Mots-clés français / French Keywords

Réacteur nucléaire

;

Ecorceur

;

Molybdène

;

Faisceau électronique

;

Tokamak

;

Carbone

;

Deutérium

;

Erosion

;

Résistance mécanique

;

Conductivité thermique

;

Réacteur fusion nucléaire

;

Interaction solide plasma

;

Graphite

;

Matériau isotrope

;

Mots-clés espagnols / Spanish Keywords

Reactor nuclear

;

Descortezador

;

Molibdeno

;

Haz electrónico

;

Tokamak

;

Carbono

;

Deuterio

;

Erosión

;

Resistencia mecánica

;

Conductividad térmica

;

Reactor fusión nuclear

;

Interacción sólido plasma

;

Grafito

;

Material isótropo

;

Localisation / Location

INIST-CNRS, Cote INIST : 9265, 35400018611526.1990

Nº notice refdoc (ud4) : 21652326



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