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SEWG Fuel Retention July 2008 © Matej Mayer Fuel retention in ASDEX Upgrade tungsten coatings M. Mayer, M. Balden, K. Krieger, S. Lindig, O. Ogorodnikova, V. Rohde, K. Sugiyama, and ASDEX Upgrade Team Max-Planck-Institut für Plasmaphysik, EURATOM Association, Garching, Germany Retention in ASDEX Upgrade from post-mortem studies First results on modelling of ASDEX Upgrade retention Surface modifications (blistering)
SEWG Fuel Retention July 2008 © Matej Mayer Retention in ASDEX Upgrade from post-mortem studies
SEWG Fuel Retention July 2008 © Matej Mayer W coverage in AUG 2002 – 2007 Step by step replacement of C tiles by W coated tiles 3 – 4 µm W-PVD on most tiles 200 µm plasma-sprayed W at outer strike point
SEWG Fuel Retention July 2008 © Matej Mayer Deuterium inventory C-dominated campaign 2002/2003 D on divertor tiles 0.9 – 1.3 g D below roof baffle 0.4 g in 3000 s Full W campaign 2007 D on divertor tiles 0.15 – 0.23 g D below roof baffle 0.03 g in 3000 s 6A 4 9B 1A 3A 4940 s 2620 s
SEWG Fuel Retention July 2008 © Matej Mayer Deuterium inventory in inner divertor of all-W machine Correlation between distributions of C and D D inventory in inner divertor still dominated by C-codeposition 6A 4
SEWG Fuel Retention July 2008 © Matej Mayer Deuterium inventory in outer divertor of all-W machine D inventory in outer divertor dominated by trapping in W Deep diffusion (> 3 µm) observed for VPS layers at outer strike point 3B 1
SEWG Fuel Retention July 2008 © Matej Mayer AUG divertor: Evolution of D inventory Carbon dominated machine Total D-inventory dominated by inner divertor and remote areas All-W machine Boronizations result in high D-inventory, co-deposition with B (2005/2006 campaign) D-inventory dominated by trapping in VPS-layers at outer strike point Decrease of total D-inventory by factor 5 – 10 from C-dominated to all-W
SEWG Fuel Retention July 2008 © Matej Mayer First results on modelling of ASDEX Upgrade retention
SEWG Fuel Retention July 2008 © Matej Mayer Retention as function of fluence VPS-W Laboratory and AUG data (VPS-W from tile 1) available Polycrystalline W Laboratory and AUG data (Langmuir probes) available 4 µm PVD-W No data (with known fluence/retention) available Assume same properties as polycrystalline W 4 µm thickness taken into account I 4µm = 0.67 x I Total
SEWG Fuel Retention July 2008 © Matej Mayer 1 3B 2 3A Incident fluence Outer divertor Ion fluence measured with Langmuir probes on tile 1 Extrapolation to tiles 2, 3A Fluence on 3B from erosion in 2004/2005 Inner divertor Assume identical number of ions as outer divertor 4.2 m 2, 10 22 ions/m 2 s Roof baffle Assume 3.3 m 2, 10 21 ions/m 2 s Main chamber Assume 8 m 2, 10 21 ions/m 2 s and 32 m 2, 10 19 ions/m 2 s Codeposition with C 1.9x10 19 C-atoms/s, D/C = 0.4
SEWG Fuel Retention July 2008 © Matej Mayer 1 3B 2 3A Modelling: Outer divertor Good agreement between model and experimental data, keeping the uncertainties in mind
SEWG Fuel Retention July 2008 © Matej Mayer Modelling: Full ASDEX Upgrade Good agreement for outer divertor Model gives too high inventory for inner divertor More realistic fluence data necessary
SEWG Fuel Retention July 2008 © Matej Mayer Modelling: Work in progress Ion fluences for inner divertor K. Krieger, July 2008 Temperature history of outer divertor for 2007 campaign A. Herrmann, July 2008 Inventory in 4 µm PVD-W as function of fluence O. Ogorodnikova, October 2008
SEWG Fuel Retention July 2008 © Matej Mayer Surface modifications (blistering)
SEWG Fuel Retention July 2008 © Matej Mayer = 10 26 D/m 2, T irr = 550 K = 10 26 D/m 2, T irr = 583 K Lab studies, 38 eV D-ions: BlistersAUG, Langmuir-probes: Blisters V. Kh. Alimov
SEWG Fuel Retention July 2008 © Matej Mayer Lab studies, 38 eV D-ions: BlistersAUG, Langmuir-probes: Blisters Blisters are not hollow! V. Kh. Alimov
SEWG Fuel Retention July 2008 © Matej Mayer Lab studies, 38 eV D-ions: BlistersAUG, Langmuir-probes: Blisters Often (always?) widened cracks (grain boundaries?) below blisters V. Kh. Alimov
SEWG Fuel Retention July 2008 © Matej Mayer T irr = 515 K T irr = 567 K Lab studies, 38 eV D-ions: SpongeAUG, Langmuir-probes: Sponge Sponge-like structures are observed V. Kh. Alimov
SEWG Fuel Retention July 2008 © Matej Mayer Summary Retention in ASDEX Upgrade: Decrease of trapped D in divertor by factor 5 – 10 from C-dominated to all-W machine D-inventory in all-W machine determined by deep diffusion into W at outer strike point Modelling of ASDEX Upgrade data: First modelling using experimental laboratory/AUG data and measured AUG fluxes Good agreement for outer divertor, further work needed for inner divertor Surface modifications: Blister-like structures observed in laboratory studies and AUG polycrystalline W No blister cap, not hollow (but often/always cavity/crack observed) These are no classical blisters! Naming?
SEWG Gas Balance 2007 © Matej Mayer First results on deuterium depth profiling in W tiles M. Mayer 1, V.Kh. Alimov, V. Rohde 1, J. Roth 1, A. Herrmann.
PSI 2008 Toledo May 2008 © Matej Mayer Carbon balance and deuterium inventory from a carbon dominated to a full tungsten ASDEX Upgrade M. Mayer a, V. Rohde.
ITPA Avilla January 2008 © Matej Mayer Surface modifications and blistering of tungsten exposed in ASDEX Upgrade M. Mayer, M. Balden, S. Lindig, J. Roth,
Kazuyoshi Sugiyama, SEWG meeting on Fuel retention, Garching, July Contribution of Boron on the D retention in the AUG full-W wall regime Max-Planck-Institut.
ITPA May 2007 © Matej Mayer Carbon Erosion and Transport in ASDEX Upgrade M. Mayer 1, V. Rohde 1, J.L. Chen 1, X. Gong 1, J. Likonen 3, S. Lindig 1, G.
K. Sugiyama, 9th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials, Salamanca, June 2-3, Max-Planck-Institut für Plasmaphysik.
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,
Kazuyoshi Sugiyama, SEWG meeting, Culham, July Outline: 1.Introduction 2.Experimental procedure 3.Result 4.Summary Kazuyoshi Sugiyama First.
Report IPP Garching EU Task Force PWI Meeting, Cadarache Oct Max-Planck-Institut für Plasmaphysik compiled by Arne Kallenbach (IPP - EU-PWI.
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.
Kazuyoshi Sugiyama, SEWG meeting on Fuel retention, Garching, July Max-Planck-Institut für Plasmaphysik D retention and release behaviour of.
M. Mayer SEWG Fuel Retention June Sample Analysis for TS, AUG and JET: Depth Profiling of Deuterium M. Mayer Max-Planck-Institut für Plasmaphysik,
J. Roth, EU PWI TF, SEWG Fuel Retention, Garching, July 19, 2010 Report on: WP10-PWI /IPP/PS Multi machine scaling of fuel retention for ITER Validation.
1TPL Dismantling Project Review 08/12/06 Bernard Pégourié TORE SUPRA Association EURATOM-CEA D program: Specific experiments before dismantling Purpose:
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.
Annual High-Z /Metal PFC SEWG Meeting, Ljubljana 1-2 October 2009 Studies of Plasma-Wall Interactions Post mortem characterization of exposed tungsten.
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.
EU PWI Task Force V. Philipps, SEWG mixed materials, JET ITER-like Wall Project : Material choice, issues to investigate and role of new SEWG ITER-like.
V.Philipps, SEWG Gas balance and fuel removal, JET, , Association EURATOM – FZJ Effect of disruptions on fuel release from JET walls V. Philipps,
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation K. Schmid SWEG Deuterium retention in graphite samples exposed to beryllium-seeded.
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.
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,
J. Roth: ITPA SOL/DIV, Avila, Jan Prediction of ITER T retention levels with W PFCs J. Roth, and the SEWG Fuel retention of the EU Task Force on.
Th Loarer - SEWG on Fuel retention – JET, July Th Loarer with special thanks to S Brezinsek, J Bucalossi, I Coffey, G Esser, S Gruenhagen.
K. Krieger, SEWG Meeting on Material Migration and ITER Material Mix, JET, Max-Planck-Institut für Plasmaphysik Carbon local transport and redeposition.
Overview of recent work on carbon erosion, migration and long-term fuel retention in the EU-fusion programme and conclusions for ITER V. Philipps a Institute.
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.
No 1 V. Philipps, SEWG Fuel retention, July 2010, Garching Joint TEXTOR, MAGNUM and PISCES experiments on retention in W and mixed W/C system V. Philipps,
© Olga Ogorodnikova, 2008, Salamanka, Spain Current status of assessment of Tritium inventory in all-W device O.V. Ogorodnikova and E. d’Agata.
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.
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation K. Schmid SEWG meeting on mixed materials Parameter studies for the Be-W interaction Klaus Schmid.
1 Effects of simultaneous impurity ion irradiation on tritium behavior near tungsten surface Y. Ueda, M. Fukumoto, H. Kashiwagi, Y. Ohtsuka (Osaka University)
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation Interaction of nitrogen plasmas with tungsten Klaus Schmid, A. Manhard, Ch. Linsmeier, A. Wiltner,
Trilateral Euregio Cluster A.Kreter, V.Philipps et al "Retention in W, Mo and graphite samples simultaneously exposed to SOL plasma in TEXTOR" Assoziation.
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.
1 Max-Planck-Institut für Plasmaphysik 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila ELM resolved measurements of W sputtering MPI für Plasmaphysik.
M. Reinelt, K. Schmid, K. Krieger SEWG High-Z Ljubljana Max-Planck-Institut für Plasmaphysik EURATOM Association, Garching b. München, Germany.
ERO modelling of local 13 C deposition at the outer divertor of JET M. Airila, L. Aho-Mantila, S. Brezinsek, P. Coad, A. Kirschner, J. Likonen, D. Matveev,
Vienna University of Technology (TU Wien) slides provided by F. Aumayr EURATOM – ÖAW: Contribution of the Austrian Fusion Association 2006 Innsbruck University.
1 Max-Planck-Institut für Plasmaphysik 9th ITPA Meeting on Divertor and SOL Physics, 10/5/07 Initial operation of ASDEX Upgrade with 100 % tungsten PFCs.
Member of the Helmholtz Association Carbon based materials: fuel retention and erosion under ITER-like mixed species plasma conditions Arkadi Kreter et.
R. Doerner, ITPA SOL/DIV meeting, Avila, Jan. 7-10, R. P. Doerner, G. De Temmerman, M.J. Baldwin, D. Nishijima Center for Energy Research, University.
Member of the Helmholtz Association Fuel retention in carbon materials Arkadi Kreter et al.
1 Th LoarerGas balance and fuel retention – EU TF on PWI – 29 October 2007 Madrid Th Loarer with contributions from D Borodin, C Brosset, J Bucalossi,
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.
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.
1 Th LoarerGas balance and fuel retention – EU TF on PWI – 13 November 2006 Th Loarer with contributions from C. Brosset 1, J. Bucalossi 1, P Coad 2, G.
1. Qualifying carbon as PFC Erosion (see report S. Brezinsek ) along plasma wetted areas, effect of substrate Local C migration to gaps Fuel retention.
1Th LoarerGas balance and fuel retention – IAEA Chengdu – 18 October 2006 TEC Euratom Th Loarer with contributions from C. Brosset 1, J. Bucalossi 1, P.
1B. PégouriéDITS progress report 27/04/07 Euratom EXPERIMENTAL CAMPAIGN No reliable estimation of the wall inventory WI ~ ??? D atoms (Tsitrone,
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