C. Björkas, K. Vörtler and K. Nordlund Department of Physics, University of Helsinki Joint TFE-SEWG - Material Migration and Material Mixing meeting MD.

Slides:



Advertisements
Similar presentations
J. Roth, EU PWI TF, SEWG Fuel Retention, Cadarache, June 15, 09 Tritium inventory: Joint international scaling for ITER WP09-PWI-01-01/IPP/PS Status by.
Advertisements

Report on SEWG mixed materials EU PWI TF meeting Madrid 2007 V. Philipps on behalf of SEWG members Mixed material formation is a among the critical ITER.
R. Doerner, Oct. 18, 2005 EU PWI TF meeting, France Beryllium and carbon mixed-material studies R. P. Doerner, M. J. Baldwin, J. Hanna and D. Nishijima.
Annual High-Z /Metal PFC SEWG Meeting, Ljubljana 1-2 October 2009 Studies of Plasma-Wall Interactions Post mortem characterization of exposed tungsten.
A new look at the specification of ITER plasma wall interaction and tritium retention J. Roth a, J. Davis c, R. Doerner d, A. Haasz c, A. Kallenbach a,
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation Interaction of nitrogen plasmas with tungsten Klaus Schmid, A. Manhard, Ch. Linsmeier, A. Wiltner,
PWI Modelling Meeting – EFDA C. J. OrtizCulham, Sept. 7 th - 8 th, /8 Defect formation and evolution in W under irradiation Christophe J. Ortiz Laboratorio.
Molecular Dynamics modelling of mixed layer formation K. Nordlund, C. Björkas, N. Juslin, K. Vörtler Accelerator Laboratory, University of Helsinki P.
WP10-PWI (02)/TEKES/BS(PS) Characterization of retention mechanisms in AUG Monitoring meeting of the EFDA PWI SEWG on Gas Balance and Fuel Retention,
M. Reinelt, K. Schmid, K. Krieger SEWG High-Z Ljubljana Max-Planck-Institut für Plasmaphysik EURATOM Association, Garching b. München, Germany.
R. Doerner, EU PWI Task Force Meeting, Frascati, Italy, Oct , 2008 US-EU Collaboration on Mixed Materials for ITER: Past, Present and Future R. P.
Kazuyoshi Sugiyama, SEWG meeting, Culham, July Outline: 1.Introduction 2.Experimental procedure 3.Result 4.Summary Kazuyoshi Sugiyama First.
R. Doerner, 8 th EU PWI Task Force Meeting, Warsaw, Poland, Nov. 4-6, 2009 Directions of the US-EU Collaboration on Mixed Materials for ITER R. P. Doerner,
Experiments about carbon removal and codeposit inhibition J.A. Ferreira, F.L. Tabarés, W. Bohmeyer and A. Markin, I. Tanarro, V. Herrero.
Development of analytical bond- order potentials for the Be-C-W-H system C. Björkas, N. Juslin, K. Vörtler, H. Timkó, K. Nordlund Department of Physics,
Vienna University of Technology (TU Wien) slides provided by F. Aumayr EURATOM – ÖAW: Contribution of the Austrian Fusion Association 2006 Innsbruck University.
SEWG Fuel Retention July 2008 © Matej Mayer Fuel retention in ASDEX Upgrade tungsten coatings M. Mayer, M. Balden, K. Krieger, S. Lindig, O. Ogorodnikova,
CIPS SEWG FR, JET 2008C. Hopf O 2 /He glow discharge cleaning: Experience at IPP Christian Hopf, Volker Rohde, Wolfgang Jacob Max-Planck-Institut für Plasmaphysik.
Joint SEWGs-TFE meeting S. Brezinsek22/07/2008 TF E Impact of N 2 on carbon chemistry in JET S. Brezinsek, Y. Corre and TFE.
V.Philipps, SEWG Gas balance and fuel removal, JET, , Association EURATOM – FZJ Effect of disruptions on fuel release from JET walls V. Philipps,
TFE Th Loarer – SEWG – 12 September Euratom Th Loarer V Philipps 2, J Bucalossi 1, D Brennan 3, J Brzozowski 4, N Balshaw 3, R Clarke 3, G Esser.
D retention and release behaviour of Be/C/W mixed materials
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation K. Schmid SEWG meeting on mixed materials Parameter studies for the Be-W interaction Klaus Schmid.
PWI questions of ITER review working groups WG1 and WG8 : Materials Introduction EU PWI TF V. Philipps, EU PWI TF meeting, Oct 2007, Madrid V. Philipps,
R. Doerner, EU SEWG meeting, JET. July 9-10, 2007 Recent Results from PISCES Program R. P. Doerner, M. J. Baldwin, G. De Temmerman, J. Hanna, D. Nishijima,
Member of the Helmholtz Association Carbon based materials: fuel retention and erosion under ITER-like mixed species plasma conditions Arkadi Kreter et.
P. Coad, J. Likonen, H. Bergsåker, M. Rubel, I. Uytdenhouwen, A. Widdowson JET mixed Be/C/O layers SEWG meeting on mixed materials, , JET.
1SEWG Fuel removal - Glow improvement for JET D. Douai22-23 July 2008 EFDA Task Glow discharge improvement for JET D. Douai 1, D. Garnier 1, S. Brémond.
R. Doerner, EU SEWG meeting, JET. July 9-10, 2007 Co-deposition/Co-implantation R. Doerner, M. Baldwin, G. De Temmerman, D. Nishijima UCSD K. Schmid, Ch.
Institute for Plasma Physics Rijnhuizen D retention in W and mixed systems in Pilot-PSI G. De Temmerman a, K. Bystrov a, L. Marot b, M. Mayer c, J.J. Zielinski.
6 th EU PWI TF Meeting Madrid, Oct Tritium Inventory in ITER: Laboratory data and extrapolation from tokamaks Th Loarer, J Roth, S Brezinsek, A.
D retention in O-covered and pure beryllium
H and He cluster formation in W Krister Henriksson Accelerator laboratory.
18 th International Conference on Plasma Surface Interaction in Controlled Fusion Toledo, Spain, May 26 – 30, Deuterium trapping in tungsten damaged.
Spectroscopy of hydrocarbon in low temperature plasmas : Results from JT-60U T. Nakano J apan A tomic E nergy A gency, Ibaraki, Japan. 6-9/11/2006 ITPA.
1 EFFECTS OF CARBON REDEPOSITION ON TUNGSTEN UNDER HIGH-FLUX, LOW ENERGY Ar ION IRRADITAION AT ELEVATED TEMPERATURE Lithuanian Energy Institute, Lithuania.
The removal of surface atoms due to energetic particle bombardment
L.B. Begrambekov Plasma Physics Department, Moscow Engineering and Physics Institute, Moscow, Russia Peculiarities, Sources and Driving Forces of.
PISCES R. Doerner, ITPA SOL/DIV meeting, Avila, Jan. 7-10, 2008 Mixed plasma species effects on Tungsten M.J. Baldwin, R.P. Doerner, D. Nishijima University.
Y. Ueda, M. Fukumoto, H. Kashiwagi, Y. Ohtsuka (Osaka University)
X-Ray Photoelectron Spectroscopy of Interfaces
Deuterium retention mechanisms in beryllium M. Reinelt, Ch. Linsmeier Max-Planck-Institut für Plasmaphysik EURATOM Association, Garching b. München, Germany.
R. Doerner, IAEA CRP on H in Materials, Vienna, Sept. 26, 2006 Mixed-material studies in PISCES-B R. P. Doerner, M. J. Baldwin, J. Hanna and D. Nishijima.
Sachiko Suzuki 1, Akira Yoshikawa 1, Hirotada Ishikawa 1, Yohei Kikuchi 1, Yuji Inagaki 1, Naoko Ashikawa 2, Akio Sagara 2, Naoaki Yoshida 3, Yasuhisa.
Iain D. Boyd and Brandon Smith Department of Aerospace Engineering University of Michigan Ann Arbor, MI Molecular Dynamics Simulation of Sputtering.
R. P. Doerner, 2 nd PMIF Meeting, Juelich, Sept , 2011 Plasma interactions with Be surfaces R. P. Doerner, D. Nishijima, T. Schwarz-Selinger and.
W coating of CFC tiles for the JET new wall - Task Agreement: JW6-TA-EP2-ILC-05 Manufacturing and testing of W-coated CFC tiles for installation in JET.
*This work was supported by the United States Department of Energy
ASIPP Study on C-W interactions by Molecular Dynamics Simulations Zhongshi Yang, Q. Xu, G. -N. Luo Institute of Plasma Physics, Chinese Academy of Sciences,
Effects of tungsten surface condition on carbon deposition
Photo physics and photo chemistry of ice films on graphite Department of Applied Physics Chalmers and Göteborg University Dinko Chakarov Johan Bergeld.
R. Doerner, ITPA SOL/DIV meeting, Avila, Jan. 7-10, Be deposition on ITER first mirrors: layer morphology and influence on mirror reflectivity G.
Molecular Dynamics Study of Ballistic Rearrangement of Surface Atoms During Ion Bombardment on Pd(001) Surface Sang-Pil Kim and Kwang-Ryeol Lee Computational.
1 Deuterium retention and release in tungsten co- deposited layers G. De Temmerman a,b, and R.P. Doerner a a Center for Energy Research, University of.
MOLIBDENUM MIRRORS WITH COLUMN NANOGRAIN REFLECTING COATING AND EFFECT OF ION- STIMULATED DIFFUSION BLISTERRING RRC «Кurchatov Institute» А.V. Rogov, К.Yu.Vukolov.
CMS HIP Plasma-Wall Interactions – Part I: In Fusion Reactors Helga Timkó Department of Physics University of Helsinki Finland.
10th ITPA conference, Avila, 7-10 Jan Changes of Deuterium Retention Properties on Metals due to the Helium Irradiation or Impurity Deposition M.Tokitani.
Korea Institute of Science and Technology Seung-Hyeob Lee, Churl-Seung Lee, Seung-Cheol Lee, Kyu-Hwan Lee, and Kwang-Ryeol Lee Future Technology Research.
Introduction to Plasma-Surface Interactions Lecture 5 Sputtering.
Erosion and Deposition in Tokamaks Christian Schulz Institut für Energieforschung - Plasmaphysik Assoziation EURATOM- Forschungszentrum Jülich Trilateral.
Sputtering. Why? Thin layer deposition How? Bombarding a surface with ions which knocks out molecules from a target which in turn will redeposit onto.
Member of the Helmholtz Association Fuel Retention and Erosion of Metallic Plasma-Facing Materials under the Influence of Plasma Impurities A. Kreter 1,
1 ITC-22, November 2012, Toki, Japan 1 Modelling of impurity transport, erosion and redeposition in fusion devices: applications of the ERO code A. Kirschner.
Tatyana Sizyuk Ahmed Hassanein School of Nuclear Engineering
Presented by T. Sugie (ITER-IT) N. Yoshida (Kyushu University, Japan)
ITERに係わる原子分子過程 Atomic and Molecular Processes in ITER SHIMADA, Michiya ITER International Team Annual Meeting of Japan Society of Plasma Science and Nuclear.
Studies of impurity migration in TEXTOR by local tracer injection
Elina Pajustea,b*, Gunta Kizanea, Ieva Igaunea
Multiscale modeling of hydrogen isotope transport in porous graphite
Deuterium retention for sample temperature of 500 K
Presentation transcript:

C. Björkas, K. Vörtler and K. Nordlund Department of Physics, University of Helsinki Joint TFE-SEWG - Material Migration and Material Mixing meeting MD study of erosion of Be and WC under D bombardment

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 2 ITER First wall: Beryllium Divertor strike point: CFC Divertor baffle and dome: Tungsten Plasma: D + T How does Be erode due to plasma impact? How does the mixed WC erode?

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 3 Method We bombarded beryllium and WC surfaces with D ions In the Be case, we used both initially rough and perfect (0001), (1120) ones For WC, both C and W determined surfaces were used eV for Be and eV for WC Flux ~2·10 28 m -2 s -1 Cell of ~3000 atoms Distance 5 Å Fixed bottommost layers, temperature control at borders

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 4 D irradiation of Be Sputtering is seen at 7 eV A large fraction of Be is eroded as BeD molecules at low energies Exps. are from Nishijima et al. Plasma Phys. Control. Fusion 50 (2008) at fluxes 1-3·10 22 m -2 s -1 and temperatures < 400 K New experiments are coming soon Chemical sputtering!

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 5 D irradiation of Be

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 6 D irradiation of Be

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 7 D irradiation of Be The movie shows a swift chemical sputtering process Low-energetic D ions release Be atoms from the surface by breaking Be-Be bonds The SCS was not believed to be present in metals This is possible since a surface Be atom that has bonds with D, has a weakened binding to the surface At low energies, Be atoms are likely to have D neighbours The figure shows the initial neighbours of the sputtered Be atoms

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 8 D irradiation of WC A clear preferential sputtering of C was seen in the WC irradiation Agrees with experimental findings

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 9 D irradiation of WC 300 eV D on WC resulted in collapsing amorphization First ~1000 impacts: creation of defects in sample In the following: D 2 accumulation, collapsing of structure C: gray W: magenta D: light gray

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 10 D irradiation of WC Flaking was also observed C: gray W: magenta D: light gray

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 11 Conclusions The D bombardment of Be showed a clear chemical effect The swift-chemical sputtering mechanism is present WC get amorphous due to D bombardment Even flaking is seen in a few cases

Joint TFE-SEWG Material Migration and Material Mixing meeting - Carolina Björkas 12 Thank you!