The EU Plasma Wall Interaction Task Force:Recent Achievements and Plans

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This work is a part of IAEA CRP(2008-2012): Characterization of Size, Composition and Origins of Dust in Fusion Devices presentations located at http://www-amdis.iaea.org/CRP/Dust/Presentations2/


R. Zagórski
EFDA CSU Garching

Contents

European Fusion Development Agreement and EU PWI Task Force

  • The overall fusion programme remains coordinated by the Commission in the frame of Euratom
Dust2Zagorski1.jpg

Joint Undertaking for ITER “Fusion for Energy” (F4E)

  • Domestic Agency to provide and manage EU contribution to ITER
  • EU Contribution to Broader Approach
  • Located in Spain (Barcelona)

European Fusion Development Agreement (EFDA)

  • Agreement between all EU fusion labs and Euratom
- All EU Laboratories/Institutions working on Fusion are parties to EFDA
  • Coordinated research (physics in support to ITER, longer term technology and JET)
- Collective use of JET
- Reinforced coordination of physics and technology in EU laboratories
- Training
- EU contributions to international collaborations outside F4E

EU Plasma Wall Interaction Task Force (EU PWI TF)

  • The aim of the PWI Task Force is to concentrate European research on the most urgent problems in the field of PWI for ITER and future devices, and to propose scientific and technological concepts to overcome these problems
  • Task Force Plasma-Wall Interaction:
- Main orientations at Annual General Meeting
- Contact Persons from 23 associations + JET TF E1/E2 and FT, EFDA, F4E, ITER IO
- 7 Special Expert Working Groups with Annual specialised meetings

Topics

  • ITER high priority research needs are strongly related to PWI problems
  1. Disruption/ Runaway Mitigation: Heat loads, runaway electrons
  2. ELM Control/ Mitigation
  3. Plasma Facing Materials: Physics basis for ITER reference scenarios with W/ Be PFCs and C removal
  4. Scenario Development
  5. Diagnostics: Dust/Hot dust, divertor erosion, mirrors and H/D/T inventory
  • ITPA Div SOL : 5 topics
  1. Transient heat loads : ELMs and disruptions
  2. Material erosion: Material migration, High-Z Materials and ITER-like Material Mix
  3. Tungsten R&D: Material migration, High-Z Materials and ITER-like Material Mix
  4. Dust : Dust in fusion devices
  5. Fuel Retention and Removal

EU PWI TF Meetings

  • PWI Annual Meeting, 3-5 November, Vienna, Austria
  • EFDA Meeting on modelling activities of EU-PWI Task Force: 7-8 September 2010, Culham, JET
  • SEWG Meetings:
- Dust and Fuel Removal: 8-9 June, Garching
- Material Mix & Material Migration: 30 June – 02 July, Jülich
- Fuel Retention: 19-21 July, Garching
- High Z Materials and Liquid Metals: 21-23 July, Garching
- Transients and Heat Loads: 1- 2 September, Jülich


Recent achievements of the PWI TF: highlights of 2009

  • Evidence for threshold in chemical erosion at 1-2 eV;
  • Development of transport codes: ELMs and gaps in ERO, grid extension to the wall ongoing in SOLPS
  • H retention in W confirmed to be low:
impact of He bombardment, simulation of neutron damage
porosity network in CFC characterized by high resolution tomography
  • First characterization of runaway electrons in Tore Supra and TEXTOR;
similar valves in MAST, TEXTOR and JET for massive gas injection (MGI) studies
modelling effort started for runaways and MGI (FZK)
  • Performance of N seeded scenarios well established in full W AUG and nitrogen wall pumping evidenced;
improved plasma performance with liquid lithium limiter in FTU
  • Coordinated experiments on ICRF cleaning in TEXTOR, Tore Supra, AUG as well as in JET under TFE/H
  • Dust trajectories investigated in several devices using fast cameras
  • Exploration of ternary systems (Be-C-W, Be-O-W) (IPP, MedC)
benchmarking of ERO-TRIDYN ongoing (collab. with the PISCES-B)

Work programme 2010-2011 : dust & fuel removal

  • Bilateral collaborations :
– mixed materials : PISCES (US) → EFDA PWI TF
– material damage : plasma guns (RF) → F4E, but modelling + dust = PWI TF
  • Including recent ITER requests
– disruptions/runaways
– W R&D
– divertor re-attachment heat loads
– IC wall conditionning
  • Integrated plasma operation : impact of impurity seeding
– erosion, mixed material, fuel retention
  • Strengthening of modelling for extrapolation to ITER and DEMO
– Interpretative modelling for benchmarking tools used for ITER simulations (SOLPS, ERO, DIVIMP …)
– in close connection with ITM-TF (code development)

References

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