Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– 2005 1 EU-PWI Task Force & EFDA Plasma Edge Technology Programme.

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

1E. Tsitrone PWI TF meeting, 4-6/11/2009, Warsaw Euratom 2010 WP for the PWI TF : Tasks agreements and priority support The EU PWI TF under new EFDA :

EU-PWI Taskforce EU PWI TF Meeting Nov. 4 – 6, 2009, Warsaw Summary of the PSI facility review meeting presented by R. Neu based on the Summary of the.

Slide Oct 2005, EFDA PWI meeting, CEA CadaracheI.S. Landman, FZ-Karlsruhe FZK Investigations on Wall Surfaces and Tokamak Plasma 1 Forschungszentrum.

Report IPP Garching EU Task Force PWI Meeting, Cadarache Oct Max-Planck-Institut für Plasmaphysik compiled by Arne Kallenbach (IPP - EU-PWI.

EU Plasma-Wall Interaction TF – Meeting Frascati SEWG Erosion & Transport S. Brezinsek Institut für Energieforschung –Plasmaphysik.

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CIEMAT – 10 – EFDA Plasma Edge Technology Programme Monitoring of 2006 Activities.

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.

E. Tsitrone, EU PWI TF meeting, oct 2007, Madrid1 E. Tsitrone, J. Roth, A. Loarte, J. Paméla The EU-PWI Task Force: Task agreements for 2008 EU PWI.

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,

Laboratorio Nacional de Fusión Asociación EURATOM-CIEMAT PWI activities at CIEMAT (Madrid) presented by F. Tabarés Laboratorio Nacional de Fusión por Confinamiento.

1 3rd meeting Working Group 5. 2 Agenda WG5 2nd Meeting Agenda: Discuss existing proposals Indicate missing proposals Allocate persons to develop proposals.

ITER & dust Dust = major issue in term of ITER safety In vessel dust quantities: extrapolation from current experiments In vessel dust diagnostics & removal.

R.Zagórski, PWI-TF Annual Meeting, Frascati, October 2008 EFDA Plasma Edge Technology Programme Monitoring of 2008 Activities Roman Zagórski European Fusion.

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – Jozef Stefan Institute – 11 – EU-PWI Task Force & EFDA Plasma Edge Technology.

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – Jozef Stefan Institute – 11 – Report on EU-PWI SEWG on Transient Loads Alberto.

TORE SUPRA Association EURATOM-CEA Philipps, Huber, Schweer, Sergienko, Brezinsek, Mertens, Zlobinski & Grisolia, Hernandez, Roche, Pocheau, Davi, Semerok.

Th Loarer - SEWG on Fuel retention – JET, July Th Loarer with special thanks to S Brezinsek, J Bucalossi, I Coffey, G Esser, S Gruenhagen.

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,

SEWG Meeting HIGH-Z, Ljubljana, October 2009 I. Tungsten distribution on limiters after WF 6 injection in TEXTOR II. SEM and EDX of Melted Tungsten Rods.

Kazuyoshi Sugiyama, SEWG meeting, Culham, July Outline: 1.Introduction 2.Experimental procedure 3.Result 4.Summary Kazuyoshi Sugiyama First.

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,

EU-PWI TF Task Force meeting, Cadarache Oct EU-PWI CONTRIBUTIONS FROM IFP F. Ghezzi Istituto di Fisica del Plasma, C.N.R., EUR/ENEA/CNR Ass.,

Experiments about carbon removal and codeposit inhibition J.A. Ferreira, F.L. Tabarés, W. Bohmeyer and A. Markin, I. Tanarro, V. Herrero.

K. Krieger, SEWG Meeting on Material Migration and ITER Material Mix, JET, Max-Planck-Institut für Plasmaphysik Carbon local transport and redeposition.

Vienna University of Technology (TU Wien) slides provided by F. Aumayr EURATOM – ÖAW: Contribution of the Austrian Fusion Association 2006 Innsbruck University.

EU Plasma-Wall Interaction TF – Meeting FZJ SEWG Chemical Erosion S. Brezinsek TEC 1 Report of the Special Expert Working Group on Chemical.

SEWG Fuel Retention July 2008 © Matej Mayer Fuel retention in ASDEX Upgrade tungsten coatings M. Mayer, M. Balden, K. Krieger, S. Lindig, O. Ogorodnikova,

Report on SEWG ITER like Material Mix V. Philipps on behalf of SEWG working group* Decided during EU -TF meeting Cadarache, 2005 Work programme defined.

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.

R.Zagórski, SEWG Meeting, Culham, July New EFDA and PWI Work Programme R.Zagórski EFDA CSU Garching Acknowledgements: J.Pamela, J.Roth, E.Tsitrone.

1TPL Dismantling Project Review 08/12/06 Bernard Pégourié TORE SUPRA Association EURATOM-CEA D program: Specific experiments before dismantling Purpose:

Institut für Energieforschung - Plasmaphysik EURATOM Assoziation – FZJ TEC A. Litnovsky et al., Meeting of the EU TF PWI SEWG on mixed materials, JET,

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

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.

1. Qualifying carbon as PFC Erosion (see report S. Brezinsek ) along plasma wetted areas, effect of substrate Local C migration to gaps Fuel retention.

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

V.Philipps, EFPW Padua, Dec 2005 Introduction Report on the European Task Force on Plasma Wall Interaction 2005 V. Philipps, J. Roth, A. Loarte on behalf.

Max-Planck-Institut für Plasmaphysik EURATOM Assoziation K. Schmid SEWG meeting on mixed materials Parameter studies for the Be-W interaction Klaus Schmid.

Member of the Helmholtz Association Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ A. Litnovsky et al., Progress report on the.

Slide Nov 2006, EFDA PWI meeting, LjubljanaI.S. Landman, FZ-Karlsruhe Modelling on Wall Surfaces and Tokamak Plasma Consequences of ITER Transient.

1E. Tsitrone PWI TF meeting, 27-29/10/2008, Frascati Euratom International context : ITPA (International Tokamak Physics Activity) Changes in the ITPA.

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.

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,

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CIEMAT – 10 – Report on EU-PWI SEWG on Transient Loads and Future Work Alberto.

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,

Jerome Pamela PWI meeting, 31 October New Horizons for EFDA PWI meeting, October 2007 Jerome Pamela EFDA Leader.

J. Roth Bilateral Agreements EU-DOE: e.g.: PISCES operation (following talk by Russ Doerner) Bilateral Agreement EU-Russia: collaboration on Material damage.

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.

1E. Tsitrone PWI TF meeting, 27-29/10/2008, Frascati Euratom 2009 WP for the PWI TF : Tasks agreements and priority support The EU PWI TF under new EFDA.

Max-Planck-Institut für Plasmaphysik

Transient heat load tests with Nd:YAG laser Main results of EFDA TW3-TPP/ERCAR PWI Task Force meeting – CEA Cadarache October 2005 Douglas dHulst,

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,

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.

1 PWI - related work at VR Marek Rubel (VR) Projects within ILW : Beryllium coatings for inner wall cladding (with MEC, UKAEA, FZJ, UCSD, TEKES) Development.

Extension of IEA Implementing Agreement on Large Tokamak Facilities Presented to Committee on Energy Research Technologies October 18-19, 2005 Paris, France.

Analysis of samples exposed to Pilot–PSI Plasma P. Paris, A. Hakola, K. Bystrov, G. De Temmerman, M. Aints, I. Jõgi, M. Kiisk, J. Kozlova, M. Laan, J.

Y. Ueda, M. Fukumoto, H. Kashiwagi, Y. Ohtsuka (Osaka University)

D. Tskhakaya ADAC meeting, Cadarache /16 Molecular Data in Tokamak edge Modelling D. Tskhakaya Association EURATOM-ÖAW, University of Innsbruck,

Introduction of 9th ITPA Meeting, Divertor & SOL and PEDESTAL Jiansheng Hu

Background Long term tritium retention is one of the most critical issues for ITER during the tritium phase. It is mandatory to evaluate the long term.

B WEYSSOW 2009 Coordinated research activities under European Fusion Development Agreement (addressing fuelling) Boris Weyssow EFDA-CSU Garching ITPA 2009.

Analysis of samples exposed to Pilot–PSI Plasma

Presentation transcript:

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– EU-PWI Task Force & EFDA Plasma Edge Technology Programme Alberto Loarte, Joachim Roth, Volker Philipps

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Outline 1.Background to EFDA Plasma Edge Technology Programme and Integration with EU-PWI Task Force 2. Description of Existing Tasks & Status Details to be found in 3. Plans for new Tasks in Discussion of Priorities for 2007 (ELE or post-ELE EFDA ?)

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Background Need of fundamental Understanding of PWI Processes Well defined Laboratory Experiments Specific Modelling and Extrapolation to ITER Contributions from Associations without voluntary Physics Programme Financial Volume (2005): 1 M (20% sub.) 5.1.a, 250 k (40% sub.) 5.1b (0.8 M in 5.1.a, 250 k in 5.1b for 2006) EU Task Force aims to better integrate Technology and Physics Aspects of the EFDA Plasma Edge Technology Programme

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Integration with EU-PWI TF Topics (I) Tasks in 2002/2003/2004/ Erosion behaviour Chemical Erosion of C by D/Be, TW2-TPP-ERDEP () (EU-US) Sputtering of W and Be, TW3-TPP-ERTUBE (~ 60% ) SEWG Chemical Erosion of C, TW4-TPP-ERCAR (~ 80% ) SEWG C/W/Be mixed-material formation, TW5-TPP-CARWBER (EU-US) 2. Material transport and re-deposition Flake Formation from Deposits, TW2-TVM-CFC2 () Scavenger Technique, TW3-TPP-SCAVOP () SEWG C x H y Formation and Re-deposition in ITER Geometries, TW4-TPP-TRIDEP Erosion/deposition metal wall + C divertor TW5-TPP-TILCAR Midplane and Divertor W macro-brush studies in ASDEX-Upgrade UT4-TUNAUG & UT5-MBWAUG () Already reported at last years meeting () Reported this year

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Integration with EU-PWI TF Topics (II) 3. Fuel recycling, retention and removal (2 SEWGs) Optimisation of He-O Glow for C-H removal, TW5-TPP-HEGLO Characterisation PFC Oxidation Damage, TW5-TPP-TILCAR T removal by non-O 2 oxidative methods, TW4-TPP-TRIREMA-B T retention in ITER-like material mixes and T surf, TW5-TPP-RETMIX 4. Off-normal heat loads (SEWG) Modelling of Disruptions and ELMs, TW3-TPP-DISELM () Validation of ELM Damage Modelling, TW3-MATDAM (~ 30% ) (EU-RF) ELM-Disruption exposed Target Characterisation, TW4-TARCAR (~ 40% ) W and CFC damage and plasma evolution in ITER, TW5-TPP-ITERTRAN Modelling of Be damage under Disruptions/ELMs, TW5-TPP-BEDAM (fut.EU-RF) W and CFC under-threshold damage studies, TW5-TPP-REPELM

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Integration with EU-PWI TF Topics (III) 5. Edge modelling, erosion and deposition modelling Improvements to ERO Code and ITER Modelling, TW3-TPP-ERMOD () MD Modelling of Erosion Processes, TW4-TPP-CARWMOD () W Erosion and Edge Plasma Contamination in ITER, TW5-TPP-TUNMOD 6. Edge and SOL physics Improvements to B2-Eirene for ITER Modelling, TW3-TPP-NEUTMOD () Modelling of n-n and n- effects in ITER divertor, TW5-TPP-ITERNEUT 7. Task force relevant diagnostics Speckle Interferometry for Erosion, TW0-T438/01 () Laser Ablation Techniques for Film Deposition, TW3-TPP-ERDIAG ()

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (I) ERTUBE: High T surf erosion of metals (IPP + PISCES-B under EU-US collaboration) R. Doerner + K. Schmid + J. Roth Au High T surf erosion of metals is a general property for low and high Z metals that requires T surf > 0.8 T melt & Fluxes > m -2 s -1 & low particle incident energies

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (II) ERTUBE: Composition of redeposits in Be C experiments in PISCES-B (IPP + PISCES-B under EU-US collaboration) Many samples analysed exposed to a range of experimental conditions to determine surface layer structure and composition PSI 2004, M.Baldwin, et al.

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (III) ERCAR: Synergistic effects of C erosion with impurity ions (IPP) Enhanced chemical sputtering by noble gas impurity atoms is confirmed for He, Ne, Ar ion ~ 180 (Ar), 30 (Ne) Enhancement of chemical erosion decreases slightly with atomic mass at low impact energies ITER conditions: Y phys (Ar, Ne) = 0, Y(Ar|D) ~ 0.6,Y(Ne|D) ~ 0.4, R Ar ~ 1000, R Ne ~ 100 C (ion|D)/ C (D) = Y C (ion|D)/(Y chem /R ion ) 0.06 (Ar) 0.4 (Ne) Small effect if Y chem ~ 1% (in agreement with CARWMOD results)

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (IV) SCAVOP : Determination scavenger effect dependence on conditions (IPP) Decrease of deposition with N 2 reproduced but scavenger effect ? Clear formation of volatile molecules (HCN), but also CH 3 and NH 3 increase with N 2 & enhanced N 2 + sputtering of a-C:H layers C 2 H 2 (C 2 H large source of deposits in the experiments) decreases dramatically with N 2 is this the dominant effect ?

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (V) MATDAM + TARCAR: Targets were characterised by FZJ in February and arrived at TRINITI at the end of July (modelling by FZK, analysis FZJ + ENEA-CNR+Frascati) m) (x MJ/m 2 ) Experiments have started already with the plasma gun calibration and low power exposure experiments (~ 0.5 MJ/m 2, 500 s)

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (VI) CARWMOD : MD modelling of W plasma-wall interactions (FZK, TEKES) Emphasis of W compound effects and W blistering FZK Studies of W-O system under D flux TEKES Studies of W-C system under D flux TEKES W blistering under D and He flux Example Result He E inc = 50/100 eV) on W forms bubbles that escape W without causing blister

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (VII) NEUTMOD : n-n effects are not negligible in ITER B2-Eirene has been upgraded to handle these effects (including MAR) (FZJ) for same q pk P DT goes up with n-n col. for same pumped DT S DT goes down (colder gas with n-n col.)

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (VIII) TW0-T : Erosion diagnostic with speckle interferometry (CEA) Technique tested in ideal realistic conditions produces an ideal resolution of ~10 m 3 method can resolve depths from 2000 m to 50 m with a 10 m resolution Implementation in tokamak requires addressing vibration + large observation area further tests in CEA and (if successful) in Tore-Supra will be pursued Proposed tokamak diagnostic set-up

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (IX) ERDIAG-a : Diagnosis of retention by laser desorption Technique tested in lab conditions with well characterised films Technique demonstrated in TEXTOR with non-optimum laser with good results Diagnostic design for JET approved aiming at demonstration in divertor plasmas

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Description of Tasks and Status (X) ERDIAG-b : Diagnosis of retention by LA-OES (or LIBS) Laser Ablation Optical Emission Spectroscopy (CEA) Technique tested in lab conditions with well characterised films Technique demonstrated on TEXTOR tiles Diagnostic incorporated in plans for JET laser ablation system for de-tritiation D/C TEXTOR tile front D/C TEXTOR tile back The critical issue is to optimise crater (depth + profile) to guarantee relevant desorption (by strata)

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Plans for new Tasks in 2006 Mixed Materials Studies Study of W/C/O deposits from tokamaks (ASDEX Upgrade, TEXTOR, etc.) with focus on mixed-material formation and T retention Modelling of mixed-material formation processes and T retention Study of W-C-H (+O) system Study of the Be-C-D (+O) system Proof of principle for erosion deposition in-situ diagnostic Ideas ? Demonstration of T-removal techniques for mixed-materials Ideas ? Experimental studies of dynamics of molten layers under transient loads in tokamaks Ideas ? Dedicated ITER PWI modelling ? Ideas ?

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Money matters : History and Facts Budget allocated for TPP area of EFDA Technology programme roughly constant since 2003 (20% reduction in 2006 EFDA Technology due to start of ITER construction) Real requested/allocated budget increases with time (in 2005 hopefully by 80-90%) Increase of requested/allocated budget reflects interest of EFDA management on PWI issues + the good work of EU-PWI Task Force!!

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Priorities for 2007 Experiments/Modelling on erosion/redeposition in lab experiments and fusion devices Mixed Materials Studies T retention and removal Diagnostics for in-situ T retention measurement Diagnostics for in-situ erosion/redeposition measurements Dedicated PWI modelling in ITER (erosion/redeposition in main Q DT =10 scenario + ramp-up phase) Studies of Be damage under ELMs and disruptions More ideas are very welcome !!!!!

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CEA – Cadarache 17 – 10– Conclusions EFDA TPP Technology Programme is well integrated with EU-PWI Research Programme and producing ITER-relevant results As recognised by EFDA and ITER management Two major EFDA Collaborations with US (PISCES-B) and RF (TRINITI) on-going New large collaboration about to be approved with RF (Kurchatov + TRINITI) on Be damage under ITER transient loads EU staff to collaborate in-situ in the experiments (Euratom Mobility) + EU industry to provide targets (+ few Be coated targets?) + destructive analysis of targets to be done in EU labs (new EFDA tasks in 2007) Many Associations involved : CEA, CIEMAT, ENEA-Frascati, ENEA-CNR Milano, FOM-NRG, FZJ, FZK, IPP, IST, ÖAW, TEKES, and VR How to get new Associations involved in Technology Programme ?