How to do wall conditioning in ITER ? # B tor cycles is limited GDC inefficient in B Drawbacks of ECWC, Taylor Ion cyclotron wall conditioning (ICWC) J.

Slides:

Advertisements

Similar presentations

Presentation on RF Heating by - Saurabh Kumar Vij

Advertisements

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati may 2011 Aula B Brunelli ) 1 of 18 slides Research strategy of JT60SA.

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.

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

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,

EU Plasma-Wall Interaction Task Force meeting November 2006 Lubljana, Slovenia "Interaction of a liquid Gallium jet with ISTTOK's edge plasmas: first.

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.

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

Alberto Loarte EU Plasma-Wall Interaction Task Force Meeting – CIEMAT – 10 – ITER Design Review Activities on Steady State and Transient Power.

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.

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,

SIMS and RBS analysis of the recent 13 CH 4 experiment J. Likonen, P. Coad, A. Hakola, D. Hole, M. Rubel, J. Strachan, A. Widdowson Joint TFE-SEWG meeting.

V.Philipps, SEWG Gas balance and fuel removal, JET, Energy Research – Plasma Physics | Association EURATOM – FZJ Ion Cyclotron Wall Conditioning.

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.

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

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,

1B. PégouriéDITS progress report 27/04/07 Euratom EXPERIMENTAL CAMPAIGN No reliable estimation of the wall inventory WI ~ ??? D atoms (Tsitrone,

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,

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.

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,

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.

Introduction to Plasma-Surface Interactions Lecture 6 Divertors.

Enabling Technology on Alcator C-Mod Jim Irby MIT-PSFC.

Barbora Gulejová 1 of 12 Centre de Recherches en Physique des Plasmas SPS Annual Meeting in Lausanne, 14/2/2006 SOLPS5 modelling of ELMing H-mode on TCV.

ITER WC Review Started : March 2007 (4 meetings) Official Members : M Shimada, D. Whyte, V. Rohde, N Ashikawa, JS Hu and C Grisolia Several contributors:

1 ITPA - DSOL - TorontoS. Brezinsek TEC Hydrocarbon spectroscopy on EU tokamaks S. Brezinsek on behalf of the EU task force for Plasma-Wall Interaction.

Effects of ICRF conditioning on the first wall in LHD N. Ashikawa, K. Saito, T. Seki, M. Tokitani, Y. Ohtawa 1), M. Nishiura, S. Masuzaki K. Nishimura.

Physics of fusion power

A. Canton, S. Dal Bello 13 th IEA/RFP Workshop Density control in RFX-mod A. Canton, S. Dal Bello Consorzio RFX, Padova, Italy.

IOS-5.2 Maintaining ICRH Coupling in expected ITER regime Spokes person: M. Goniche M.-L. Mayoral (JET), R. Pinsker (DIII-D), L. Colas (TS), V. Bobkov.

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.

Association EURATOM-Belgian State LPP-ERM/KMS SCK-CEN ULB M.Van Schoor, V.Massaut, D.Carati.

ITPA-9, Avila, Spain, Impact of ICRF on impurity production in TEXTOR Presented by Marek Rubel Alfvén Laboratory, Royal Institute of Technology,

Divertor/SOL contribution IEA/ITPA meeting Naka Nov. 23, 2003 Status and proposals of IEA-LT/ITPA collaboration Multi-machine Experiments Presented by.

1 HT-7/EAST ASIPP Oxidation wall conditionings on HT-7 and EAST superconducting tokamaks J.S Hu, J.G Li, Y.P Zhao EAST Team Institute of.

THE WEST PROJECT AND RELATED ACTIVITIES AT CEA-IRFM 24/09/2012ADAS WORKSHOP | PAGE 1 CEA | 10 AVRIL 2012 R. Guirlet, J. Bucalossi, M. Firdaouss, Y. Marandet,

TORE SUPRA 1 D. Douai Recent results on Ion Cyclotron Wall conditioning 15 April 2010 Recent results on ICWC D. Douai 1, A. Lyssoivan 2, V. Philipps 3,

US ITER UFA Meeting APS-DPP Savannah, GA Ned Sauthoff (presented by Dale Meade) November 15, 2004 US In-kind Contributions and Starting Burning Plasma.

Discussions and Summary for Session 1 ‘Transport and Confinement in Burning Plasmas’ Yukitoshi MIURA JAERI Naka IEA Large Tokamak Workshop (W60) Burning.

Member of the Helmholtz Association A. Litnovsky et al., Third rehearsals on PSI-18, Jülich, Monday, May 19, 2008 Investigations of castellated structures.

Transport of deuterium - tritium neutrals in ITER divertor M. Z. Tokar and V.Kotov Plasma and neutral gas in ITER divertor will be mixed of deuterium and.

The propagation of a microwave in an atmospheric pressure plasma layer: 1 and 2 dimensional numerical solutions Conference on Computation Physics-2006.

RF codes for Transp Transp User Course 2014 Jim Conboy.

A.Lyssoivan – 18PSI, Toledo, Spain 27/05/ Influence of Toroidal and Vertical Magnetic Fields on Ion Cyclotron Wall Conditioning in Tokamaks Presented.

D. Tskhakaya et al. 1 (13) PSI 18, Toledo July 2008 Kinetic simulations of the parallel transport in the JET Scrape-off Layer D. Tskhakaya, R.

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

FOM - Institute for Plasma Physics Rijnhuizen Association Euratom-FOM Diagnostics and Control for Burning Plasmas Discussion All of you.

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.

EAST ASIPP ICR-Wall conditioning in EAST J.S Hu, J.G Li and EAST Team Institute of Plasma Physics, Chinese Academy of Sciences, P.O.Box 1126, Hefei, Anhui.

Integrated Operation Scenarios ITPA Remaining duties ITPA CC meeting & IEA/ITPA JE planning meeting –12 – 14 (15) December 2011, Cadarache –Ide, Sips and.

T Loarer – TFE meeting – 20 February TORE SUPRA Association Euratom-Cea Gas Balance - fuel retention in JET T Loarer, J Bucalossi, D Brennan*, G.

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

Summary of RF-Related Presentations at the 2011 EPS Meeting G. Taylor NSTX Physics Meeting July 25, 2011 NSTX Supported by 1.

Seminar in ASIPP, 11 Dec Page 1 Status of ITER Project and Issues of Plasma-Wall Interaction Michiya Shimada With contribution from Richard Pitts.

045-05/rs PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Taming The Physics For Commercial Fusion Power Plants ARIES Team Meeting.

MCZ MCZ NCSX Mission Acquire the physics data needed to assess the attractiveness of compact stellarators; advance understanding.

Click to edit Master title style Preparing JET for T and DT operation 26 th January 2016 George Sips Presented at: PPPL, Princeton, USA.

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.

Dynamic fuel retention and release under ITER like wall conditions in JET V. Philipps 1, T. Loarer 2, M. Freisinger 1, H.G.Esser 1, S. Vartanian 2, U.

Evaluation of a Field Aligned ICRF Antenna in Alcator C-Mod 24th IAEA Fusion Energy Conference San Diego, USA October S.J. Wukitch, D. Brunner,

TFE 3/2/2004 – Fuel retention in JET - J. Bucalossi / T. Loarer Assessment of fuel retention in JET : Contingency – 2 shifts on 6 th of february E. Tsitrone.

Modélisation non-linéaire des interactions ondes/plasma de bord Enabling Research CEA-05 L. COLAS (PI), L. LU, P. Tamain, IRFM E. Faudot, S. HEURAUX,

Major aims of IPP-NIFS collaboration on divertor physics

ITER ICRF Scenario Demonstration in Hydrogen with 3He Minority Heating

Presentation transcript:

How to do wall conditioning in ITER ? # B tor cycles is limited GDC inefficient in B Drawbacks of ECWC, Taylor Ion cyclotron wall conditioning (ICWC) J. Roth General aims of wall conditioning: Plasma initiation - Impurities, fuel removal Control of discharge content - Isotopic ratio ITER : Tritium removal Ion Cyclotron Wall Conditioning (ICWC) on JET V. Philipps, A. Lyssoivan, D. Douai, R. Pitts, C. Schueller, T. Loarer, G. Sergienko, S. Brezinsek, J. Ongena, M. Mayoral … ICWC compatible with permanent magnetic field ICWC seems suitable – at least in C machines – for removal of impurities and tritium control by isotope exchange (TEXTOR, Tore Supra and AUG)

RF plasma production : He-D 2 ICWC Simulate D 2 -ICWC in ITER full field conditions using JET A2 ICRF antennas : BT=3.3 T and frequencies ~25 MHz and ~29 MHz thus simulating ITER operation at BT=5.3 T and 40 MHz and 46.6 MHz Simulate ITER RF conditions at full field JET only! - Optimise poloidal homogeneity (and penetration of the ICWC-plasma into the divertor throat) using a second frequency - Optimise RF power coupling (phasing of antenna straps, gas pressure and composition, antenna phasing, in particular for safe antenna operation - Check consistency with codes (deposition profile by TOMCAT/METS ) PWI : pure D 2 ICWC 1) Assess the efficiency of ICWC for T-removal on large size tokamak with divertor 2) Compile a reference dataset with a C-based PFCs for later comparison with the ILW JET : only machine with Be operation unique information for active phase in ITER! - Optimise isotopic exchange efficiency : pressure, gas-composition, RF-power waveform after breakdown - Optimize duty-cycle (RF on/ RF off). - Test plasma re-start after ICWC ITER DCR-080 (2007) : ICWC as a functional requirement for the main ICRH system ITPA experiment SOL/Div group Goals and rationales

ICWC discharge optimisation (RF part + preparation of PWI experiment) Reference ICWC discharge Preloading by 2 hours H 2 -GDC with H + )= cm -2.s -1 total fluence = 4, H/cm 2 ~ accessible reservoir in JET: D Reference H 2 -ohmic shot [H]/([H]+[D]) 10 D 2 -ICWC shots to perform change-over Reference D 2 ohmic shots [H]/([H]+[D]) - test of ohmic plasma initiation after ICWC - repeated for changeover H D Diagnostics - Neutral Particle Analyser : CX neutrals + isotopic ratio in ref ohmic shots - OES - Detailed exhaust gas composition by mass spectrometry - AGHS after cryo-pumps regeneration - pressure gauges - + others : Langmuir, Penning gauges,… Present strategy