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Journal ArticleDOI

Influence of microstructure and notch fabrication on impact bending properties of tungsten materials

TLDR
In this article, the fracture behavior of several tungsten-based alloys was characterized by standard Charpy tests which have been performed up to 1100°C in vacuum, and the influence of the microstructure characteristics like grain size, anisotropy, texture, or chemical composition as well as the effect of notch machining was investigated.
Abstract
Refractory materials, in particular tungsten base materials are considered as primary candidates for high heat load applications in future nuclear fusion power plants. Promising design outlines make use of the high heat conductivity and strength of W-1%La2O3 (WL10) as structural material. Here, the lower temperature range is restricted by the transition to a steel part and the upper operation temperature limit is defined by the onset of recrystallization and/or loss of strength, respectively. The most critical issue of tungsten materials in connection with structural applications, however, is the ductile-to-brittle transition. Another problem consists in the fact that especially refractory alloys show a strong correlation between microstructure and their manufacturing history. Since mechanical properties are defined by the underlying microstructure, refractory alloys can behave quite different, even if their chemical composition is the same. Therefore, the fracture behavior of several tungsten based alloys was characterized by standard Charpy tests which have been performed up to 1100 °C in vacuum. Due to their fabrication history (powder mixing, pressing, sintering, rolling or swaging) all materials had specific microstructures which often led to typical delamination fractures. The influence of the microstructure characteristics like grain size, anisotropy, texture, or chemical composition as well as the effect of notch machining was investigated. All results are discussed and assessed with respect to the optimization of future component fabrication for high temperature nuclear fusion applications.

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Journal ArticleDOI

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

Michael Rieth, +70 more
TL;DR: In this article, the progress of work within the EFDA long-term fusion materials program in the area of tungsten alloys is reviewed, with a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.
Journal ArticleDOI

Methods for improving ductility of tungsten - A review

TL;DR: In this paper, a critical review of the methods that have been reported in the literature for improving the ductility of tungsten in order to understand the critical factors that control the ductile (or lack thereof) in Tungsten.
Journal ArticleDOI

High temperature annealing of ion irradiated tungsten

TL;DR: In this article, high temperature annealing of pure tungsten irradiated by self-ions was conducted to elucidate microstructural and defect evolution in temperature ranges relevant to fusion reactor applications.
Journal ArticleDOI

Hardening of self ion implanted tungsten and tungsten 5-wt% rhenium

TL;DR: In this article, the authors used nanoindentation to measure the change in hardness as a function of six damage levels (0, dpa, 0.07, 0.4, 1.2, 13,dpa, and 33 dpa).
References
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Journal ArticleDOI

Power plant conceptual studies in Europe

TL;DR: The European Power Plant Conceptual Study (PPCS) as mentioned in this paper has been a study of conceptual designs of five commercial fusion power plants and the main emphasis was on system integration, focusing on five power plant models which are illustrative of a wider spectrum of possibilities.
Journal ArticleDOI

Strain-rate dependence of the brittle-to-ductile transition temperature in tungsten

TL;DR: In this article, the authors investigated the strain-rate dependence of the brittle-to-ductile transition (BDT) temperature in pre-cracked tungsten single-crystals and polycrystals.
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Development of a helium-cooled divertor: Material choice and technological studies

TL;DR: In this article, a he-cooled divertor concept has been investigated at Forschungszentrum Karlsruhe in cooperation with the Efremov Institute.
Journal ArticleDOI

Limitations of W and W–1%La2O3 for use as structural materials

TL;DR: In this paper, the impact test results on the use of dispersion strengthened tungsten for divertor structures are discussed in detail, and the impact of these results on use of tengsten as structural material for fusion-specific neutron irradiation is discussed.
Journal ArticleDOI

He-cooled divertor development for DEMO

TL;DR: In this article, a helium-cooled modular jet concept (HEMJ) has been defined as reference solution, which is based on jet impingement cooling, and the first high heat flux test results confirm the feasibility and the performance of the divertor design.
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Recent progress in research on tungsten materials for nuclear fusion applications in Europe

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