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Descripción
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| The selection of materials that could resist these extreme operating conditions is a critical issue in the future of nuclear fusion. Fusion plasma leads to heat fluxes to the plasma facing materials of 15-20 MW/m² in the divertor region. Hence, only tungsten presents appropriate resistance to ion and charge-exchange particle erosion in comparison with other materials. However, the mechanical properties of commercially available W are not yet adequate for structural purposes due to its intrinsic brittleness at relatively low temperatures, thus limiting the operating temperatures of the reactor. While several solutions have been proposed for this target, none of them has fulfilled all the requirements. In this context, the goal of this study is the characterization of a ground-breaking W material produced by means of Laser Beam Melting. Therefore, the aim of this investigation is the analysis of the thermos-mechanical behaviour of novel W-based materials for the armour and heat sink of the DEMO divertor, based on the actual design of ITER. For this purpose, flexural and fracture tests were conducted in the temperature range between 25 °C and 1200 °C and under high vacuum atmosphere. Additionally, micromechanical and physical characterization was also performed by means of micro and nanoindentation and High Temperature X-Ray Diffraction respectively. | |
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Internacional
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Si |
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Nombre congreso
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The Nuclear Materials Conference |
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Tipo de participación
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960 |
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Lugar del congreso
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Seattle, USA |
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Revisores
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Si |
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ISBN o ISSN
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0000000000 |
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DOI
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Fecha inicio congreso
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14/10/2018 |
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Fecha fin congreso
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18/10/2018 |
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Desde la página
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1 |
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Hasta la página
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1 |
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Título de las actas
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The Nuclear Materials Conference |