R.Zagórski, PWI Annual Meeting, 4-6 November 2009, Warsaw 1 Research directions under EFDA WP 2009/2010 Roman Zagórski EFDA Acknowledgements to EFDA CSU

R.Zagórski, PWI Annual Meeting, 4-6 November 2009, Warsaw1

Research directions under EFDA WP 2009/2010

Roman ZagórskiEFDA

Acknowledgements to EFDA CSU Garching, Task Forces and Topical Groups


OUTLINE:

•EFDA structure & EFDA WP 2009/2010•EFDA Meetings•HPC FF


Coordination of R&D: Coordination of R&D: EFDA Task Forces & Topical GroupsEFDA Task Forces & Topical Groups

Task Forces under EFDA PWI Task Force: Leaders E.Tsitrone (CEA) and R.Neu (IPP)

ITM Task Force: Leaders P.Strand (VR), R. Coelho (IST), LG Eriksson (CEA)

Topical Groups under EFDA

Transport Topical Group: Chairman C.Hidalgo (CIEMAT)

H&CD Topical Group: Chairman A.Becoulet (CEA)

Materials Topical Group: Chairmen S.Dudarev (UKAEA) (S.Gonzalez) M. Reith (FZK)

Diagnostics Topical Group: Chairman T.Donné (FOM)

MHD Topical Group: Chairman P.Martin (ENEA-RFX)

Emerging Technologies & DEMO oriented activities(A.Malaquias)


European Charge:European Charge:Integrated ModellingIntegrated Modelling

IAEA-TM 2009, Aix en Provence, P. Strand

EFDA SC (03)-21/4.9.2 (June 24th, 2003)


ITM StructureITM Structure

Experimental data base

Modeling data base ISIP

ISIP

IMP5IMP4IMP2IMP1

Equilibrium and LinearMHD Stability

Non linear MHD phenomena

Transport Processesand Micro-stability

Heating, Current driveand fast particles

ISIP

ISIP

ISIP

ISIP

ISIP

ISIP

IMP3

Transport code and discharge evolution

ISIP

ISIP

ISIP

ISIP

a b

MHDequilibriumand stabilitymodules

Non-linearmodules(saw-teeth,ELMs, NTMs)

c d

Transportmodels

Sourcesand sinks

e f

Interfaces toboundaries

Whole devicemodeling

ISIP = Infrastructure and Software Integration Project

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ITM TF ITM TF Work Programme 2009Work Programme 2009

Atomic, Molecular, Nuclear & Surface Physics Data (AMNS)Experimentalists and Diagnosticians Resource Group (EDRG)

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ITM TF - ITM TF - Work Programme 2010Work Programme 2010

ITM Call for participation to be launched soon (November)

PWI related tasksIntegration of edge codes (ERO, ASCOT, ASPOEL, ..) in the ITM structure:Development of relavant CPO’s, coupling with other codes (e.g. ETS + edge code (SOLPS))


Standard Tokamak operation relies on the H-mode where improved confinement comes from the edge pressure gradient

distance from axis

pre

ssure

L-mode

pedestal

H-mode

With additional power:

Steep edge pressure gradient: H-mode scenario

Separatrix

X-point

Divertor

distance from axis

EFDA Transport Topical Group

Most important physics questions revolve around the edge transport barrier


Example: turbulent transport simulationExample: turbulent transport simulation

• Core Ion transport well understood from Ion Temperature gradients instabilities,

• Electron generated micro turbulence and related transport yet to be understood,

• Transport mechanisms in the H-mode pedestal not understood.

EFDA Transport Topical Group

Study the long wave correlations and turbulent transport in the pedestalValidate the measurements from invasive diagnostics with non-invasive methods

Study the effect of rotation, impurities … on plasma transport

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R.Zagórski, PWI Annual Meeting, 4-6 November 2009, Warsaw

Call for Participation launched deadline for answers 20 November 2009

Transport TG – WP2010

Task Agreement WP10-TRA-01: L-H transition physics- L-H power threshold and ELM control techniques- Role of atomic physics mechanismsTask Agreement WP10-TRA-02: Turbulent electron transportTask Agreement WP10-TRA-03: Particle and impurity transport in standard andadvanced tokamak scenarios- Experiments on impurity transportTask Agreement WP10-TRA-04: Role of neoclassical and turbulent mechanisms inplasma rotationTask Agreement WP10-TRA-05: Statistical properties of edge turbulent transport- Diagnostics for edge turbulence-Theory and modelling of edge turbulence


Top Priority: Avoidance and Mitigation of Disruptions

“Disruptions”, abrupt termination of the plasma, need to be limited on ITER

Why ?

- transient loads on plasma facing components (erosion/melting)

- forces on vessel and in-vessel components

- recovery from disruption (loss of availability for experimentation)

How ?

- disruption avoidance (precursors) and mitigation

- operation away from stability limits (avoid too ambitious plasma operation)

Infrared view of the vessel during a disruption at JET showing the thermal loads in the plasma facing components

EFDA MHD Topical Group


STABLE

STABLE WITH CONTROL

UNSTABLE

Operation at high pressure requires qmin > 2 and active control of plasma instabilities.

Coils

EFDA MHD Topical Group

q=2q=1

Study and develop active control of plasma instabilities

MHD Topical groups addresses the performance limiting MHD instabilities: - NTMs (Neoclassic Tearing Modes),- RWM (Resistive Wall Modes)- ELMs (Edge Localized Modes)

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MHD TG – WP2010

Task Agreement WP10-MHD-01: Fast Particles Physics- Experiments on fast particle instabilities-Assessment of ITER needs and feasibility studies

Task Agreement WP10-MHD-02: Disruptions-Runaway electrons - Electromagnetic forces- Mitigation and avoidance

Task Agreement WP10-MHD-03: Sawtooth and Tearing Modes (NTMs), Edge Localised Modes (ELMs) and Stability at high Beta (RWMs)- Sawtooth and Tearing Modes- Edge Localised Modes- Stability at high Beta


Heating & Current Drive Topical GroupOrganised in 4 co-ordinating committees, corresponding to the

4 heating and current drive systems

Neutral Beam Injection (NBI)• Development of NNBI big technical challenge for ITER (> 70%)

Programme focuses on the development of NNBI advanced neutralizers

Ion Cyclotron Resonant Heating (ICRH)• Coupling in ELMy H-mode• Arc detection for component protection

Programme focuses on the development arc protection systems for ICRH


Heating & Current Drive Topical Group

Electron Cyclotron Resonant Heating (ECRH)• Recent development of 1MW Gyrotrons for ITER• Important for localized current drive for control• Inefficient for bulk current drive

Programme focuses on the Real-time Polarization Control of EC waves to avoid overheating of machine structures

Lower Hybrid Current Drive (LHCD)• Presently not credited in ITER baseline. • Only system capable of efficient off-axis bulk current drive for the

development of advanced scenarios.

Programme focuses on the development of LHCD for ITER

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H&CD TG – WP2010

HCD-01-01: Experimental simulation of non-linear burning plasmaHCD-01-02: Reliability of Plasma Operation (conditioning and initiation)ICRF assisted wall conditioning:Perform experimental and modelling studies to assess the quality of the RF-produced plasma and the efficiency of the wall conditioning actions.Identify the necessary code developments and implement them.

HCD-01-03: Reliability of ICRH and LHCDNeutral Pressure in front of RF antennasEdge plasma modelling

HCD-01-04: Reliability of ECH and ECCDHCD-01-05: Specific H&CD physics for ITERHCD-01-06: Off-axis Current Drive and rotationHCD-01-07: Fuelling PhysicsIntegration of particle control in ITER plasma scenarios simulationsReinforce the activities on integration of particle control in ITER plasma scenariossimulations. Develop predictive modelling for gas flow coupling the divertor, pumping, andduct systems.

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H&CD TG – WP2010

Task Agreement HCD-02-01: Support to European Facilities and ITER (LHCD)

Task Agreement HCD-02-02: Reliability of Neutral Beam Advanced Technologies

Task Agreement HCD-02-03: Fuelling TechnologiesPumps Systems·Assess the ITER solutions for pumping & fuelling and derive requirements for thesesystems under various DEMO configuration options (outline R&D needs, identifyimmediate and longer term actions)·Review status of pump development of interest for DEMO.·Initiate work in the area of steady-state, tritium-compatible rough pumping.


Diagnostics Topical Group• New or improved techniques for measuring key parameters

required for operation of future devices ITER/DEMO (for the machine protection, infer physical processes and parameters; and for plasma control).

– Ex. Plasma flows in divertor, isotope plasma composition, confined alpha particles.

• Measurements for physics studies, in order to improve understanding with experiments in present devices in key physics issues for ITER and DEMO.

– Turbulence measurements of the pedestal plasma

ITER and DEMO present a culture change due to the harsh environment for diagnostics in terms of heat and neutron fluencies; difficult/no access for maintenance and repairs.

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Tasks WP2008-2009 Diagnostics Topical GroupTasks WP2008-2009 Diagnostics Topical Group

TaskTask ITPA ITPA HPHP

ITER ITER HPHP

EFPWEFPW MHDMHD TransTrans H&CDH&CD DIAGDIAG PWIPWI

Plasma position reflectometryPlasma position reflectometry XX

Escaping fast alphasEscaping fast alphas XX XX

Fuel ion ratioFuel ion ratio XX

Neutron based diagnosticsNeutron based diagnostics XX

Measurement of confined alphasMeasurement of confined alphas XX XX

Development of edge current measurementsDevelopment of edge current measurements XX XX

Long range correlations in edge transport Long range correlations in edge transport barriersbarriers

XX XX

Heat load controlHeat load control XX

Material deposition and composition of wallsMaterial deposition and composition of walls XX XX XX

DEMO specific diagnostics constraints (WG)DEMO specific diagnostics constraints (WG) XX

Feedback control (WG)Feedback control (WG) XX

Data analysis and calibration (WG)Data analysis and calibration (WG) XX

The annual meeting of DTG was held on April 1st and 2nd, where preliminary progressesof these tasks were discussed together with proposals for WP 2010

DTGDTG

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Heat load controlHeat load control

First robust and fast algorithms need to be developed for the identification of First robust and fast algorithms need to be developed for the identification of patterns in the IR images that are useful for the control objectives at hand. patterns in the IR images that are useful for the control objectives at hand. Optimization of the implementation of the algorithms to meet the speed Optimization of the implementation of the algorithms to meet the speed requirements needed for the real time applications.requirements needed for the real time applications.

This task is assigned to This task is assigned to ENEA-RFXENEA-RFX (recognition algorithms)(recognition algorithms)

Material deposition and composition of wallsMaterial deposition and composition of walls

Comparative experiments on Comparative experiments on laser-induced breakdown system (LIBS) laser-induced breakdown system (LIBS) to define to define the optimized parameters for a future implementation of a LIBS device on a the optimized parameters for a future implementation of a LIBS device on a tokamaktokamak

This task is assigned to This task is assigned to ENEAENEA (LIBS)(LIBS)TARTU, CEA TARTU, CEA MEdC (tiles with coating to test LIBS)MEdC (tiles with coating to test LIBS)IPPLMIPPLM

Tasks DTG WP2008-2009 of interest for PWITasks DTG WP2008-2009 of interest for PWIDTGDTG

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Tasks WP2010 Diagnostics Topical GroupTasks WP2010 Diagnostics Topical Group

Call for proposals launched on October 15th , deadline November 20th

Tasks of interest for PWI

Diagnostics for protection of plasma facing components

Next annual meeting: Garching, March 2010. Reporting tasks WP08-09 and kick-off WP2010

DTGDTG


EFDA Meetings 2009

1. EFDA meeting on Fuelling and Particle ControlGarching 19-20 March 2009

2. EFDA Workshop on DiagnosticsGarching 1-2 April 2009

3. EFDA Technical Meeting on PSI FacilitiesGarching 18 June 2009 (R..Neu)

4. ITM Taskforce Task Force Project Leaders and General Annual MeetingFZJ, Juelich 6-11 September 2009

5. Transport Topical Group 2nd Annual meetingUKAEA, Culham 16-18 September 2009

• EFDA Technical Meeting: status of DEMO achievements under EFDAGarching 29- 30 September 2009

• 17th European Fusion Physics Workshop7-9 December 2009 , Velence, Hungary

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“Fuelling/Pumping or Particle Control”

Transversal activity across TG and TF

•Fuelling, Particle Control and Tritium economy in future devices•Burn and Particle Control•Pumping, divertor operation and SOL physics•Fuelling and Pumping Technologies•Fuelling and H&CD•Other fuelling applications

FuellingFuelling Meeting, Meeting, 19-20 March 2009 19-20 March 2009

← Sessions

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1- Pellet fuelling experiments to validate ITER scenarios. Assist in pellet fuelling database for extrapolation to ITER

2- Modelling of pellet physics: drift, dispersion and evaporation in particular in the pedestal, as well as impact on the plasma such as the L-H power threshold, ELM triggering.

3- Reinforced activity on integration of particle control in ITER plasma scenarios simulations:

- Analysis of the consequences of slow ITER pumping rate on wall conditioning (GDC and RF) and on scenarios (compatibility with radiative divertor).

- Predictive modelling for gas flow coupling the divertor, pumping, and duct systems (also for DEMO) (detailing leaks -> pumping efficiency per species).

EFDA WP Programme 2010: Fuelling physics

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DEMO Meeting, DEMO Meeting, 29- 30 September 200929- 30 September 2009

Aim of the meeting:Aim of the meeting:

•Make the point of the progress achieved under EFDA in the main issues for DEMO Make the point of the progress achieved under EFDA in the main issues for DEMO as an integrated systemas an integrated system•Give an input to the DEMO working group recently established by CCE-FU/F4E, for a Give an input to the DEMO working group recently established by CCE-FU/F4E, for a unified EU approach the next R&D activityunified EU approach the next R&D activity

Sessions: 1) Introduction - Physical assumption2) DEMO as a complex system (D. Maissonier)3) Reliability and control (safety, availability, plasma control and performance, diagnostics) (K. Lackner)4) Power handling (walls / divertor) (P. Lorenzetto)5) Maintenance (Tritium & dust removal, remote handling) (A. Tesini)6) Tritium self-sufficiency (M. Gasparotto) 7) Round table: General discussion and possible input for the CCE-FU/F4E DEMO working group

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Need for a more integrated approach DEMO as a complex system requires many problems, technical and

physical, to be tackled consistently respect to each other

Physics R&D: it is essential to have an accompanying tokamak -- answers from ITER too late for the “fast track”--

Technology R&D: more effort to be put on

- materials sciences (+ IFMIF construction)- development of the fundamental subsystems# breeding blanket for the T self-sufficiency # H&CD for profile control# high T cooling for efficient thermal energy conversion etc...

Trade-off performance for reliabilityThe performance parameters cannot be independently optimized, large

limitation coming from power handling and control Important questions:

Quasi-continuous or Steady State? Electricity Production - Amount and efficiency?H&CD systems – how many?

Conclusion Conclusion

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Conclusion Conclusion

Critical Issues:Divertor and PFC

Divertor is a (THE) major component impacting on plasma scenarios and physics: a realistic technological limit on power handling is a key ingredient for DEMO specifications (< 20 MW/m2??)

Need for testing and developing advanced concepts:

Configurations for increased flux expansion, Super X

Tungsten: still some crucial issues: “fuzz” production; sputtering due to impurities (high radiating plasmas), erosion. Recycling

Liquid metals: attractive (unaffected by disruption) but very limited experience

Remote HandlingFuel Cycle – Tritium self-sufficiency (TBR > 1.18)

EFDA WP for DEMO to be developed soon!!!

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17th European Fusion Physics Workshop17th European Fusion Physics Workshop7th - 9th December 20097th - 9th December 2009

Sessions: Chairs:

Specifications for tungsten as plasma facing material V.Philips (FZJ)and as structural material

Status of W technologies M.Rieth (FZK)

Status on the scientific understanding of S.L. Dudarev (UKAEA)W and W-alloys material properties

W as a plasma facing component (PSI issues) R. Neu (IPP)

Development of integrated tokamak operating E. Joffrin (JET-EFDA)scenarios compatible with W PFCs

Use of Tungsten in fusion Use of Tungsten in fusion devicesdevices

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HPC-FFHPC-FF

High Performance Computer for Fusion ApplicationsHigh Performance Computer for Fusion Applications

•Peak theoretical performance: ~ 100 TFlop/s Achieved efficiency - 89.5% (Linpack test)

• Operating since – 6 August 2009

•Located in the Jülich Supercomputing Centre

•1080 compute nodes: Bull NovaScale R422-E220 racks with 54 nodes each

•Processor: Intel Xeon X5570 (Nehalem-EP) quad-core, 2.93 GHz

•Memory: ~250 TB

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HPC board

allocation of resources (CPU time and high level support) chooses HLST team members monitors operation and exploitation of facility annual work programme for STAC approval user representation, meetings ….

S. Günter (IPP; chair), N. Baluc (CRPP), X. Garbet (CEA), R. Giannella (EU), T. Hender (UKAEA), F. Iannone (ENEA), S. Potempski, P. Strand (Chalmers), R. Zagorski (EFDA; secretary), (K. Wolkersdorfer (FZJ))

Selected by EFDA SC ( 2 year mandate) with the following obligations:

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Call for proposalsCall for proposals20092009

• End of 2008: call for proposals for the usage of HPC-FF in 2009End of 2008: call for proposals for the usage of HPC-FF in 2009

• 45 proposals received requesting a total of 53 MCPU hours (45 proposals received requesting a total of 53 MCPU hours (20 MCPU hours allocated for 20 MCPU hours allocated for projects)projects)

• Associations involved: CEA, Associations involved: CEA, VRVR, CRPP, Denmark, FZJ, IPP, Latvia, OAW, UKAEA, CRPP, Denmark, FZJ, IPP, Latvia, OAW, UKAEA

• Call still open …(Call still open …(new proposal from TEKESnew proposal from TEKES) )

• Proposals refereed by members of the HPC boardProposals refereed by members of the HPC board , criteria: , criteria: Relevance for Fusion HPC compatibility Scientific Excellence EU collaborations

85% CPU hours = 25 MCPU hours for projects10% HLST5% guaranteed access by associations

projects to be found on www.efda-hlst.eu

20201010•Call for proposals for the usage of HPC-FF in 2010

- Launched on 27th October -Deadline: 31st December 2009 (external referees)

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High level support teamHigh level support team

Main aims:Main aims:

• • Parallelise and optimise codesParallelise and optimise codes

• • Improve the performance of existing codesImprove the performance of existing codes

• • Initiate the transfer of other codes to multiprocessors platformsInitiate the transfer of other codes to multiprocessors platforms

• • Make existing codes into community tools and merge codes if needed;Make existing codes into community tools and merge codes if needed;

• • Choose algorithms, mathematical library routine to adapt applications to the computer architectures Choose algorithms, mathematical library routine to adapt applications to the computer architectures

• • Train young scientists to the use of HPC systems Train young scientists to the use of HPC systems

• • Provide consultancy to existing HPC specialists in the Associations;Provide consultancy to existing HPC specialists in the Associations;

Composed of (12 members):Core Team (IPP) -5 members (5ppy) + 7 members (4 ppy) in other Associations

2008/2009•Call for participation in the HLST (reopened in June 2009)•Advertisement for Positions in the Core Team in Garching•Call for use of the HLST resources (5 (of 10) projects selected)2009/2010Call for proposals for the support from HLST in 2010 - Launched on 27th October -Deadline: 31st December 2009

Documents

R.Zagórski, PWI Annual Meeting, 4-6 November 2009, Warsaw 1 Research directions under EFDA WP 2009/2010 Roman Zagórski EFDA Acknowledgements to EFDA CSU