Tungsten as a Structural Divertor Material
Authors:
- 27 October 2010
- conference paper
- Published by Trans Tech Publications, Ltd. in Advances in Science and Technology
- Vol. 73, 11-21
Abstract
Refractory materials, in particular tungsten base materials are considered as primary candidates for structural high heat load applications in future nuclear fusion power plants. Promising helium-cooled divertor design outlines make use of their high heat conductivity and strength. The upper operating temperature limit is mainly defined by the onset of recrystallization but also by loss of creep strength. The lower operating temperature range is restricted by the use of steel parts for the in- and outlets as well as for the back-bone. Therefore, the most critical issue of tungsten materials in connection with structural divertor applications 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 physical and mechanical properties are influenced by the underlying microstructure, refractory alloys can behave quite different, even if their chemical composition is the same. Therefore, creep and thermal conductivity have been investigated using typical commercial tungsten materials. Moreover, the fracture behavior of different tungsten based semi-finished products 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, forging, or swaging) these materials have specific microstructures which lead different fracture modes. The influence of the microstructure characteristics like grain size, anisotropy, texture, or chemical composition has been studied.Keywords
This publication has 11 references indexed in Scilit:
- High heat flux components—Readiness to proceed from near term fusion systems to power plantsFusion Engineering and Design, 2010
- Fracture Behaviour of Tungsten Based Alloys Depending on Microstructure and Notch Fabrication MethodFusion Science and Technology, 2009
- Power plant conceptual studies in EuropeNuclear Fusion, 2007
- He-cooled divertor development for DEMOFusion Engineering and Design, 2007
- Development of a helium-cooled divertor: Material choice and technological studiesJournal of Nuclear Materials, 2007
- Strain-rate dependence of the brittle-to-ductile transition temperature in tungstenPhilosophical Magazine, 2007
- FIB‐Nanotomography of Particulate Systems—Part I: Particle Shape and Topology of InterfacesJournal of the American Ceramic Society, 2006
- He-cooled divertor for DEMO: Experimental verification of the conceptual modular designFusion Engineering and Design, 2006
- Limitations of W and W–1%La2O3 for use as structural materialsJournal of Nuclear Materials, 2005
- Low temperature embrittlement behaviour of different ferritic-martensitic alloys for fusion applicationsJournal of Nuclear Materials, 1996