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Thermal Shock Behaviour of Different Tungsten Grades Under Varying

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Thermal Shock Behaviour of Different Tungsten Grades Under Varying Thermal Shock Behaviour of Different Tungsten Grades under Varying Conditions Von der Fakultät für Maschinenwesen der Rheinisch-Westfälischen Technischen Hochschule Aachen zur Erlangung des akademischen Grades eines Doktors der Naturwissenschaften genehmigte Dissertation vorgelegt von Oliver Marius Wirtz Berichter: Univ.-Prof. Dr.-Ing. Lorenz Singheiser Univ.-Prof. Dr. rer. nat. Bernhard Unterberg Tag der mündlichen Prüfung: 19. Juli 2012 Diese Dissertation ist auf den Internetseiten der Hochschulbibliothek online verfügbar. List of symbols and abbreviations Symbols ∆T Temperature rise . [K] ∆t Pulse duration. .[s] Absorption coefficient for electrons. .[-] λ Thermal conductivity . [WK−1m−1] µ Poisson´s ratio . [-] ν Frequency . [Hz] ρ Density . [kgm−3] σ Nuclear cross section . [barn] τE Energy confinement time . [s] Ra Arithmetic mean roughness . [µm] a Thermal diffusivity . [m2s−1] C Heat capacity . [JK−1] c Speed of light . [ms−1] −1 −1 cp Specific heat capacity . [Jkg K ] d Distance. .[m] −2 1/2 FHF Factor of heat flux . [MWm s ] I Current. .[A] Iabs Absorbed current . [A] Iinc Incident current . [A] 2 −2 KD Kinetic energy . [kgm s ] Kx Correlation constant . [-] III m Mass................................................................[kg] n Ion density . [m−3] −3 ne Electron density . [m ] P Power...............................................................[W] −2 Pabs Absorbed power density . [Wm ] S Area................................................................[m2] T Temperature. .[K] t Time.................................................................[s] T1 Correction factor . [-] Te Electron temperature . [eV] Ua Acceleration voltage . [V] Abbreviations BSE Backscattered Electron CCD Charge-Coupled Device CFC Carbon Fibre Composite CS Cross Section CTE Coefficient of Thermal Expansion DBTT Ductile-to-Brittle Transition Temperature DIFFER Dutch Institute for Fundamental Energy Research dpa Displacement Per Atom DSC Differential Scanning Calorimetry EDM Electric Discharge Machining EDX Energy-Dispersive X-ray ELM Edge Localized Mode FEM Finite Element Method FIR Far Infrared FWHM Full-Width-Half-Maximum JUDITH Juelicher Divertor Test Facility in Hot Cells IV L Longitudinal Grain Structure (in loading direction) LCMF Last Closed Magnetic Field Line LM Light Microscopy MARION Material Research Ion Beam Test Stand NIR Near Infrared pBN Pyrolytic Boron Nitride PFC Plasma-Facing Component PFM Plasma-Facing Material PG Pyrolytic Graphite PSI Plasma Surface Interaction R Recrystallised Longitudinal Grain Structure (in loading direction) RT Room Temperature SCK•CEN Studiecentrum Voor Kernenergie•Centre D’Etude De L’Energie Nucleaire SEM Scanning Electron Microscopy SOL Scrape-Off Layer T Transversal Grain Structure (in loading direction) TV Top View UTS Ultimate Tensile Strength VDE Vertical Displacement Event W-UHP Ultra High Purity Tungsten (99.9999 wt%) WT% Weight Percentage WVMW Tungsten-Vacuum-Metallizing-Tungsten V VI List of publications Parts of the results presented in this work have already been published in the following articles: M. Wirtz, J. Linke, G. Pintsuk; Thermal resistivity of tungsten grades under fusion relevant conditions; Jahrestagung Kerntechnik 2010, Compact Nr. 801 (2010). J. Linke, Th. Loewenhoff, V. Massaut, G. Pintsuk, G. Ritz, M. Rödig, A. Schmidt, C. Thomser, I. Uytdenhouwen, V. Vasechko, M. Wirtz; Performance of different tungsten grades under transient thermal loads; Nuclear Fusion 51 (7), art. no. 073017 (2011). J. W. Coenen, V. Philipps, S. Brezinsek, G. Pintsuk, I. Uytdenhouwen, M. Wirtz, A. Kreter, K. Sugiyama, H. Kurishita, Y. Torikai, Y. Ueda, U. Samm; Melt-layer ejec- tion and material changes of three different tungsten materials under high heat-flux conditions in the tokamak edge plasma of TEXTOR; Nuclear Fusion 51 (11), art. no. 113020 (2011). M. Wirtz, J. Linke, G. Pintsuk, L. Singheiser, I. Uytdenhouwen; Comparison of the thermal shock performance of different tungsten grades and the influence of microstruc- ture on the damage behaviour; Physica Scripta T145 , art. no. 014058 (2011). M. Wirtz, J. Linke, G. Pintsuk, J. Rapp, G. M. Wright; Influence of high flux hydrogen- plasma exposure on the thermal shock induced crack formation in tungsten; Journal of Nuclear Materials 420 (1-3), pp. 218-221 (2012). M. Wirtz, J. Linke, G. Pintsuk, G. De Temmerman, G. M. Wright; Thermal shock behaviour of tungsten after high flux H-plasma loading; Journal of Nuclear Materials Submitted. This work, supported by the European Communities under the contract of Association between EURATOM/Forschungszentrum Jülich, was carried out within the framework of the European Fusion Development Agreement. The views and opinions expressed herein do not necessarily reflect those of the European Commission. VII VIII Kurzfassung Thermonukleare Fusionskraftwerke sind eine vielversprechende Möglichkeit, die Ener- gieversorgung zukünftiger Generationen zu sichern. Allerdings stellt sie uns in vielen Forschungsbereichen vor enorme Herausforderungen. Ein großer Schritt hin zu einem Prototyp eines Fusionsreaktors (DEMO) wird ITER sein, welcher zurzeit in Cadar- ache in Südfrankreich gebaut wird. Eine der schwierigsten Aufgaben stellt hierbei die Auswahl von geeigneten Werkstoffen dar und ganz besonders die der dem Plasma zu- gewandten Materialien (plasma facing material, PFM). PFMs, die in einer Anlage wie ITER zu Einsatz kommen, müssen nicht nur extremen stationären und transienten thermischen Belastungen standhalten, sondern auch hohen Wasserstoff-, Helium- und Neutronenflüssen widerstehen. Materialien, die für eine solche Anwendung in Frage kommen, sind Beryllium, Wolfram und Kohlenstofffaserverstärkter Kohlenstoff (car- bon fibre composite, CFC). Wolfram ist der vielversprechendste Werkstoff für eine Anwendung im Bereich des Divertors, wo die extremsten Belastungsbedingungen herrschen und wird aller Wahr- scheinlichkeit nach auch als PFM in DEMO Verwendung finden. Aus diesem Grund konzentriert sich die vorliegende Arbeit auf die Untersuchung des Thermoschockver- haltens verschiedener Wolframsorten unter ITER und DEMO relevanten Belastungszu- ständen, um die zugrundeliegenden Schädigungsmechanismen zu verstehen und Mate- rialeigenschaften zu identifizieren, welche dieses Verhalten beeinflussen. Hierzu wurden sowohl die mechanischen und thermischen Eigenschaften, als auch die Mikrostruktur von fünf industriell hergestellten Wolframsorten charakterisiert. Anschließend wurden alle fünf Materialien bei Temperaturen zwischen RT und 600 °C in der Elektronen- strahlanlage JUDITH 1 transienten thermischen Belastungen mit Leistungsdichten von bis zu 1,27 GWm−2 ausgesetzt. Um ein weites Spektrum an Belastungsbedingungen ab- zudecken und eine übermäßige Arbeitsbelastung der Testanlage zu vermeiden, wurde die maximale Zyklenzahl auf 1000 begrenzt. Die Ergebnisse dieser Experimente er- möglichten es, unterschiedliche Schädigungs- und Rissgrenzwerte für die verschiedenen Materialien festzulegen, sowie bestimmte Materialeigenschaften zu identifizieren, die einen Einfluss auf die Lage dieser Grenzwerte und die Ausprägung der verursachten Schädigungen haben. Darüber hinaus konnte festgestellt werden, dass nicht nur die unterschiedlichen Zusammensetzung der Materialien, sondern auch die Mikrostruktur und die Rekristallisation des Materials einen wesentlichen Einfluss auf die Thermo- schockschädigung hat, wie z. B. den Rissverlauf und die Oberflächenaufrauung. Neben diesen rein thermischen Belastungen wurden Wolframproben nacheinander mit Wasserstoffplasma hoher Flussdichte und zyklischen Thermoschocks belastet. Die aus IX diesen Versuchen erhaltenen Ergebnisse sollten Aufschluss darüber geben, ob die zu- sätzliche Belastung mit hohen Teilchenflüssen einen Einfluss auf das Thermoschock- verhalten von Wolfram hat. Hierbei wurde vor allem auf die Veränderung der Thermo- schockrissparameter wie Rissabstand, -breite und -tiefe geachtet. Die Ergebnisse ha- ben gezeigt, dass besonders die Vorbelastung mit Wasserstoffplasma einen signifikanten Einfluss auf das Thermoschockverhalten von Wolfram hat. Neben der Abfolge der Be- lastungszustände konnte die Oberflächentemperatur der Wolframproben während der Plasmabelastung als weiterer Einflussparameter auf das Materialverhalten identifiziert werden. Eine der offensichtlichsten Veränderungen aufgrund der Vorbelastung mit Was- serstoff ist, dass die Thermoschockrisse nicht länger auf den elektronenstrahlbelasteten Bereich beschränkt sind. Sie breiten sich sowohl in dem Bereich, der zuvor mit Plasma belastet wurde, also auch im unbelasteten Randbereich der Wolframproben aus. Dar- über hinaus ist bei der Vorbelastung von Wolframproben mit Wasserstoff eine generelle Abnahme aller Rissparameterwerte zu beobachten. Die Kombination dieser Ergebnisse zeigt, dass das Thermoschockverhalten von Wolf- ram sehr komplex ist und von einer großen Bandbreite von Parametern beeinflusst wird. Die Auswirkungen extremer thermischer Belastungen auf unterschiedliche Wolf- ramsorten können sehr gut mittels Elektronenstrahltest simuliert und charakterisiert werden, allerdings ohne den Einfluss hoher Teilchenflüsse zu berücksichtigen. Der Ein- fluss von Wasserstoffplasma hoher Flussdichten kann aus den nacheinander erfolgten Belastungsexperimenten abgeschätzt werden. Die Ergebnisse bieten einen guten Über- blick der zu erwartenden Materialschädigung von Wolfram als PFM. Zusätzlich zeigen sie, dass die bei starken thermischen Belastungen in Kombination mit hohen Teilchen- flüssen verursachten Schädigungen an der Materialoberfläche schädlich für den Betrieb von
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