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Spark plasma sintering of tungsten-based WTaVCr refractory high entropy alloys for nuclear fusion applications

International Journal of Minerals,Metallurgy and materials 2024年第1期31卷 146-154页

作者： Yongchul Yoo Xiang Zhang Fei Wang Xin Chen Xing-Zhong Li Michael Nastasi Bai Cui Department of Mechanical&materials Engineering University of Nebraska-LincolnLincolnNE 68588USA Nebraska Center for materials and Nanoscience University of Nebraska-LincolnLincolnNE 68588USA Department of Nuclear Engineering Texas A&M UniversityCollege StationTX 77843USA

W-based WTaVCr refractory high entropy alloys (RHEA) may be novel and promising candidate materials for plasma facing components in the first wall and diverter in fusion reactors. This alloy has been developed by a powder metallurgy process combining mechanical alloying and spark plasma sintering (SPS). The SPSed samples contained two phases, in which the matrix is RHEA with a body-centered cubic structure, while the oxide phase was most likely Ta2VO6through a combined analysis of X-ray diffraction (XRD),energy-dispersive spectroscopy (EDS), and selected area electron diffraction (SAED). The higher oxygen affinity of Ta and V may explain the preferential formation of their oxide phases based on thermodynamic calculations. Electron backscatter diffraction (EBSD) revealed an average grain size of 6.2μm. WTaVCr RHEA showed a peak compressive strength of 2997 MPa at room temperature and much higher micro-and nano-hardness than W and other W-based RHEAs in the literature. Their high Rockwell hardness can be retained to at least 1000°C.

关键词： refractory high entropy alloy plasma-facing material fusion reactor spark plasma sintering

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Fabrication of W/Cu and Mo/Cu FGM as plasma-facing materials

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International Journal of Minerals,Metallurgy and materials 2000年第2期14卷 122-125页

作者： Changchun Ge Zhangjian Zhou Jiangtao Li Xiang Liu Zhengyu Xu(Laboratory of Special Ceramics and Powder Metallurgy, University of Science and Technology Beijing, Beijing 100083, China)(Southwest Institute of Nuclear Physics, Chengdu 610041, China) Laboratory of Special Ceramics and Powder Metallurgy University of Science and Technology Beijing Beijing 100083 China Southwest Institute of Nuclear Physics Chengdu 610041 China

W/Cu Functionally Graded materials (FGM) was designed not only for reducing the thermal stress caused by the mismatch of thermal expansion coefficients, but also for combining the features of W, Mo - high plasma-erosion resistance and the advantages of Cu - high heat conductivity and ductility. Four different fabrication processes for W/Cu or Mo/Cu, including hot-pressing, Cu infiltration of sintered porosity-graded W skeleton, spark plasma sintering and plasma spraying, were investigated and compared. It was foundthat the hot-pressing process is difficult to keep the designed composition gradient, while the other three processes are successful in making W/Cu or Mo/Cu FGM. Meanwhile, microstructures and composition gradients are analyzed with SEM and EDAX.

关键词： FGM plasma-facing material W/Cu and Mo/Cu alloy

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Argon-seeded plasma exposure and oxidation performance of tungsten-chromium-yttrium smart alloys

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Tungsten 2019年第2期1卷 159-168页

作者： Janina Schmitz Andrey M.Litnovsky Felix Klein Xiaoyue Tan Uwe Breuer Marcin Rasinski Stephan Ertmer Arkadi Kreter Jesus Gonzalez-Julian Martin Bram Jan Willem Coenen Christian Linsmeier Forschungszentrum Juelich GmbH Institut fuer Energie-und Klimaforschung52425 JuelichGermany Department of Applied Physics Ghent University9000 GhentBelgium School of materials Science and Engineering Hefei University of TechnologyHefei 230009China Forschungszentrum Juelich GmbH Institut fuer Engineering und Analytik52425 JuelichGermany

Tungsten-chromium-yttrium(WCrY)smart alloys are foreseen as the first wall material for future fusion devices such as Demonstration Power Plant(DEMO).While suppressing W oxidation during accidental conditions,they should behave like pure W during plasma operation due to preferential sputtering of the lighter alloying elements Cr,Y,and W enrichment of the *** this paper,the erosion performance of WCrY and W samples simultaneously exposed to deuterium(D)plasma with the addition of 1%of the projectile ions being argon(Ar)ions at an ion energy of 120 eV is *** reference to the previous experiments at 120 eV in pure D plasma,the erosion for both WCrY and W is enhanced by a factor of~*** Ar to the D plasma suppresses significant W enrichment previously found for pure D *** investigate the impact of the plasma exposure onto the oxidation performance,plasma-exposed and non-exposed reference samples were oxidised in a dry *** show,on the one hand,that the oxida-tion suppression of WCrY in comparison to pure W is preserved during the plasma *** the other hand,it becomes evident that edge effects imposed by the geometry of the samples used in plasma experiments play a significant role for the oxidation behaviour.

关键词： Tungsten-based alloys plasma-facing material Smart alloys DEMO

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