Fracture mechanical analysis of tungsten armor failure of a water-cooled divertor target |
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| Affiliation: | 1. Lehrstuhl für Werkstoffkunde und Werkstoffmechanik, Technische Universität München, Boltzmannstr. 15, 85748 Garching, Germany;2. Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching, Germany;1. JET-EFDA, Culham Science Centre, Abingdon OX14 3DB, UK;2. Forschungszentrum Jülich GmbH, Institut fuer Energie und Klimaforschung – Plasmaphysik, Juelich, Germany;3. Culham Centre for Fusion Energy, Abingdon, UK;4. Laboratory for Plasma Physics, Ecole Royale Militaire/Koninklijke Militaire School, USA;5. Karlsruhe Institute of Technology, P.O. Box 3640, D-76021 Karlsruhe, Germany;6. Institute of Plasma Physics AS CR, Za Slovankou 3, 18221 Praha 8, Czech Republic;7. Astrophysics Research Centre, School of Mathematics and Physics, Queen’s Univ. Belfast, UK;8. CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France;9. Division of Fusion Plasma Physics, KTH, SE-10044 Stockholm, Sweden;10. Max-Planck-Institut für Plasmaphysik, 85748 Garching, Germany;11. Max-Planck-Institut für Plasmaphysik, Teilinsitut Greifswald, D-17491 Greifswald, Germany;12. ITER Organization, Route de Vinon sur Verdon, 13115 Saint-Paul-lez-Durance, France;1. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, 230031, China;2. Science Island Branch of Graduate School, University of Science & Technology of China, Hefei, 230031, China;3. Hefei Center for Physical Science and Technology, Hefei, 230022, China;4. Hefei Science Center of Chinese Academy of Sciences, Hefei, 230027, China;5. ITER Organization,Route de Vinon sur Verdon, CS 90 046 13067 Saint Paul lez Durance Cedex, France;1. Institute of Advanced Energy, Kyoto University, Kyoto, Japan;2. Tokyo Institute of Technology, Tokyo, Japan;1. NRC «Kurchatov Institute», Akademika Kurchatova pl., Moscow, Russia;2. SRC RF TRINITI, Moscow Region, Russia;3. Efremov Institute, St. Petersburg, Russia;4. Institution «Project Center ITER», Moscow, Russia;5. National Research Nuclear University MEPhI, Kashirskoe sh. 31, Moscow, Russia;1. CEA, IRFM, F-13108 Saint-Paul-Lez-Durance, France;2. École Nationale Supérieure des Mines de Saint-Étienne, LGF, CNRS UMR 5307, 42023 Saint-Etienne cedex 2, France;3. University of Lyon, Ecole Nationale d’ Ingénieurs de Saint-Etienne, LTDS, CNRS UMR 5513, 42023 Saint-Etienne, France |
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| Abstract: | The inherent brittleness of tungsten at low temperature and the embrittlement by neutron irradiation are its most critical weaknesses for fusion applications. In the current design of the ITER and DEMO divertor, the high heat flux loads during the operation impose a strong constraint on the structure–mechanical performance of the divertor. Thus, the combination of brittleness and the thermally induced stress fields due to the high heat flux loads raises a serious reliability issue in terms of the structural integrity of tungsten armor. In this study, quantitative estimates of the vulnerability of the tungsten monoblock armor cracking under stationary high heat flux loads are presented. A comparative fracture mechanical investigation has been carried out by means of two different types of computational approaches, namely, the extended finite element method (XFEM) and the finite element method (FEM)-based virtual crack tip extension (VCE) method. The fracture analysis indicates that the most probable pattern of crack formation is radial cracking in the tungsten armor starting from the interface to tube and the most probable site of cracking is the upper interfacial region of the tungsten armor adjacent to the top position of the copper interlayer. The strength threshold for crack initiation and the high heat flux load threshold for crack propagation are evaluated based on XFEM simulations and computations of stress intensity factors and J-integrals. |
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| Keywords: | Divertor Tungsten armor High heat flux loads Fracture mechanics Crack Stress intensity factor |
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