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High pulse number thermal shock testing of tungsten alloys produced by powder injection molding

Loewenhoff, Th.; Antusch, S. 1; Pintsuk, G.; Rieth, M. ORCID iD icon 1; Wirtz, M.
1 Karlsruher Institut für Technologie (KIT)

Abstract:

The investigation of plasma facing materials (PFM) subjected to a large number (≥10,000) of thermal shocks is of interest to determine long term morphological changes which might influence component lifetime in and plasma performance of a fusion reactor. The electron beam facility JUDITH 2 was used to simulate these conditions experimentally. In this study eight different tungsten grades produced by powder injection molding (PIM) were investigated: Two pure tungsten grades, one with 2 wt% Y₂O₃, three with 1, 2 and 3 wt% TiC, and two with 0.5 and 1 wt% TaC. Samples of 10 × 10 × 4 mm³ were brazed to a copper cooling structure and subjected to 10⁵ thermal shocks of 0.5 ms duration and an intensity of L$_{abs}$=0.55 GW/m² (F$_{HF}$=12 MWs½/m2) at a base temperature of T$_{base}$ = 700 °C. The PIM grades showed damages in general comparable with a sintered and forged pure tungsten reference grade (>99.97 wt% W) that complies with the ITER specifications. One exception was the 2 wt% TiC doped material which failed early during the experiment by delamination of a large part of the surface. The Y₂O₃ doped material showed a comparatively good performance with respect to crack width (<15 μm) and roughening (R$_{a}$ = 0.75 μm), but showed melt droplets of ∼3–4 μm diameter, while the 1 wt% TiC doped material showed wide cracks (up to 50 μm) and strong roughening (R$_{a}$ = 2.5 μm). ... mehr


Verlagsausgabe §
DOI: 10.5445/IR/1000095281
Veröffentlicht am 09.01.2020
Originalveröffentlichung
DOI: 10.1016/j.nme.2019.100680
Scopus
Zitationen: 19
Web of Science
Zitationen: 17
Dimensions
Zitationen: 19
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Werkstoffkunde (IAM-WK)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 08.2019
Sprache Englisch
Identifikator ISSN: 2352-1791
KITopen-ID: 1000095281
HGF-Programm 31.03.09 (POF III, LK 01) Strukturmaterial f. Blanket und Divertor
Erschienen in Nuclear materials and energy
Verlag Elsevier
Band 20
Seiten Art. Nr.: 100680
Vorab online veröffentlicht am 15.05.2019
Schlagwörter Plasma facing material, Tungsten, Tungsten alloy, Powder injection molding (PIM), High heat flux
Nachgewiesen in Dimensions
Scopus
Web of Science
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