Material Mixing of Tungsten with Carbon and Helium

Journal Article · Thu May 20 00:00:00 EDT 2010 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.3447996· OSTI ID:21362069

Ueda, Y; Lee, H T ^[1]

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1. Graduate School of Engineering, Osaka University, 2-1 Yamada-Oka, Suita, Osaka 565-0871 (Japan)

In ITER, graphite and tungsten are used for divertor materials and are mixed through erosion, transport, and redeposition. Helium, a fusion reactant, is an intrinsic element in fusion plasmas that impinges on the metallic wall materials to form He bubbles. W-C mixed layers and He bubble layers greatly affect tritium retention. In this paper, impacts of W-C material mixing on erosion and hydrogen isotope retention are reviewed. Then, recent results on carbon deposition on tungsten in TEXTOR tokamak and helium effects on blistering and retention are discussed.

• OSTI ID: 21362069
• Journal Information: AIP Conference Proceedings, Vol. 1237, Issue 1; Conference: 3. ITER international summer school, Aix-en-Provence (France), 22-26 Jun 2009; Other Information: DOI: 10.1063/1.3447996; (c) 2010 American Institute of Physics; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DEPOSITION
DIVERTORS
EROSION
GRAPHITE
HELIUM
ITER TOKAMAK
LAYERS
PLASMA
TEXTOR TOKAMAK
TRITIUM
TUNGSTEN
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CARBON
CLOSED PLASMA DEVICES
ELEMENTS
FLUIDS
GASES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
METALS
MINERALS
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
RARE GASES
REFRACTORY METALS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
TRANSITION ELEMENTS
YEARS LIVING RADIOISOTOPES