Towards reliable design-by-analysis for divertor plasma facing components – Guidelines for inelastic assessment (part 1: Unirradiated)
Authors:
- 21 June 2019
- journal article
- research article
- Published by Elsevier in Fusion Engineering and Design
- Vol. 147, 111234
Abstract
No abstract availableKeywords
This publication has 22 references indexed in Scilit:
- Conceptual design studies for the European DEMO divertor: Rationale and first resultsFusion Engineering and Design, 2016
- Interpretation of the deep cracking phenomenon of tungsten monoblock targets observed in high-heat-flux fatigue tests at 20 MW/m 2Fusion Engineering and Design, 2015
- The “ductility exhaustion” method for static strength assessment of fusion structuresFusion Engineering and Design, 2015
- Overview and status of ITER internal componentsFusion Engineering and Design, 2014
- Potential and limits of water cooled divertor concepts based on monoblock design as possible candidates for a DEMO reactorFusion Engineering and Design, 2013
- Impact of plastic softening of over-aged CuCrZr alloy heat sink tube on the structural reliability of a plasma-facing componentFusion Engineering and Design, 2008
- The design of joints between elastically dissimilar components (with special reference to ceramic/metal joints)The Journal of Strain Analysis for Engineering Design, 1992
- Low-cycle fatigue behavior of oxygen-free high-conductivity copper at 300°C in high vacuumJournal of Nuclear Materials, 1984
- Tensile and low-cycle fatigue measurements on cross-rolled tungstenJournal of Nuclear Materials, 1981
- Heat Transfer and Pressure Drop of Liquids in TubesIndustrial & Engineering Chemistry, 1936