Fusion Researchnew horizonsJerome Pamela EFDA Leader

Content of the talk

Fusion strategy

ITER: a major Step

Accompanying programme

IFMIF and Materials R&D

Organisation of the European programme

Involvement of the Portuguese Association

towards DEMODEMOJETJT60SA

Towards DEMODEMOJETJT60SA

ITER: a major stepTokamak: a success story

Progress in fusion can be compared with the computing power and particle physics accelerator energy

Present machines produced significant DT fusion power TFTR (US) 10MW in 1994 and JET(EU) 16MW in 1997

A further step by a factor 5-6 in performance (n T t) to get to the reactor domain

NEXT STEP NEEDED ITER

The core of ITER Major plasma radius 6.2 mPlasma Volume: 840 m3Plasma Current: 15 MATypical Density: 1020 m-3Typical Temperature: 20 keV Fusion Power: 500 MWMachine mass: 23350 t (cryostat + VV + magnets)5,3 T on plasma axis

ITER: a major Step Scientific objective: the first burning plasma on earthA burning plasma is dominated and maintained by its own internal heat source from the DT reactions=> characterized by the power amplification factor: QQ = power generated by fusion reactions / heating power injected in the plasma fraction of plasma self-heating by fusion born a-particles: fa = Q/(Q+5) With a power amplification Q > 10, ITER will provide for the first time access to self-heated plasmas (fa > 2/3) and provide the ultimate scientific demonstration needed

ITER: a major Step

Coils of unprecedented size and performance

ITER: a major Step Demanding High Heat Flux Components

EU-supplies several ITER diagnostics

ITER - DiagnosticsLidarPolari-meter

ITER: An unprecedented international collaboration

A programme towards Fusion Energy: Accompanying ProgrammeDEMOJETJT60SA

Strong Accompanying Programme in physics in parallel to ITER construction

Includes satellite tokamaks (JET and then JT60SA)

See later description of EFDA for other activities

On the path to ITERJET6 meters 80 m316 MWITER12 meters800 m3500 MWthDiameter (plasma) Plasma Volume DT Fusion power The ITER design is based largely on the success of JET(world record)

ASDEX Upgrade3.3 meters 14 m3JET is the largest and most successful Tokamak

JET: contributing to ITER technologiesSeveral outstanding ITER-relevant technologies were / are being developed at JET

Routine performance of in-vessel remote handling tasks =>

JET is collectively used by EFDA AssociatesMore than 300 scientists from all over Europe work on this unique facility during the 2006-2007 Campaigns

JET longer term programme: developing fully integrated plasma scenarios for ITER

Required Enhancements

JET Enhancement Programme 2: EP2EP2 scope has been confirmed during 2006 (>60M investment cost)New ITER-Like Wall Enhancement of Neutral Beam Capabilities (NBE)High Frequency Pellet Injector (HFPI)Plasma Control Upgrade18 Diagnostic Projects

Shutdown foreseen to start in November 2008

Scientific exploitation 2010 and possibly beyond

JET ITER-like wall experimentITER100m2 Tungsten Low erosion high melting T Negligible T retentionOptimise lifetime & T- retentionBut high Z & melting700m2 Beryllium first wall low Z Oxygen getter Optimise plasma performanceBut large erosion & melting 50 m2 Graphite CFC Lowish ZNo melting in transientsSuperior heat shock behaviourOptimise heat flux resistanceBut large erosion & T retentionWCFCJET

EP2: Neutral beam UpgradeNB Power increase from 25 to 34 MWPulse length from 10 to 20 sPlasma scenarios will be developed closer to ITER conditions

JT-60SA (in the frame of the Broader Approach between EU & Japan) as a satellite to ITER (support to ITER during ITER operation) Enhanced flexibility in aspect ratio (A=2.6-3.1) and plasma shape. High power heating/current-drive system, 41MW for 100 s, will be prepared. High beta steady-state operation (N~4, fBS~70%) for DEMO and high density ELMy H-mode operation (ne~9x1019m-3) for ITER are planned.

A programme towards Fusion Energy: IFMIF and Materials R&DDEMOJETJT60SA

Materials R&D

Potential for limited long-lived radwaste (Moeslang)

- Requires low activation material- Eurofer already shows good prospect

14 MeV neutrons from DT reactions:He generation rate higher than from slower neutrons=> swellingRequires a specific facility (IFMIF)IFMIF and MaterialsActivation by fusion neutrons: a specific problem

Overview of the IFMIF design with major subsystems (Moeslang)IFMIF and MaterialsInternational Fusion Materials Irradiation FacilityEngineering, Validation and Design Activities starting in the frame of the EU-Japan Broader Approach

n-irradiation(~1017 n/s)Li flowECR sourceRFQDTLPIE10 MW beam heat removal with high speed liquid Li flowIrrad. Volume ~ 0.5L for 1014 n/(scm2), (20 dpa/year)Temperature: 250

Content of the talk

Fusion strategy

ITER: a major Step

Accompanying programme

IFMIF and Materials R&D

Organisation of the European programme

Involvement of the Portuguese Association

New Organisation in Europe from 2007Joint Undertaking for ITER (F4E)Domestic Agency to provide and manage EU contribution to ITERContribution to Broader Approachlocated in Spain (Barcelona) Chairman C.Varandas European Fusion Development Agreement (EFDA)Agreement between all EU fusion labs and EuratomCoordinated activities (physics in support to ITER, longer term technology)European Laboratories (associated to Euratom)

BROADER APPROACHBilateral agreement between the Government of Japan and EURATOM.three projects:IFMIF/EVEDA: Engineering Validation and Engineering Design Activities for the International Fusion Materials Irradiation Facility The Satellite Tokamak Programme (JT-60-SA): upgrade of JT60UIFERC The International Fusion Energy Research Centre : Computer Simulation Center, DEMO Design and R&D Coordination Center, ITER Remote Experimentation CenterMainly contribution in kind. European contribution from France, Italy, Spain, Germany and Switzerland. Belgium under discussion.The Broader Approach will last 10 years Allocation of Contribution of the Parties 678 M (50% JS, 50% EU)

Collective use of JET

Reinforced coordination of physics and technology in EU laboratories

Training

All EU Laboratories/Institutions working on Fusion are parties to EFDAEFDA

EFDA

Two Programmatic Objectives in the Workplan

to prepare for the operation and exploitation of ITER; to further develop and consolidate the knowledge base needed for overall fusion development and in particular for DEMO.

The achievement of these objectives shall keep the European Fusion community in a frontline position in preparation of the experimentation on ITER.

EFDA

Outline of the work

five programmatic Pilars:

1- development of plasma scenarios for ITER and DEMO,2- plasma wall interaction and plasma facing materials, 3- theory & integrated modelling,4- Emerging Fusion Technologies and Plasma Engineering Techniques, 5- Fusion as a future energy source (includes Public Information, Socio-Economics etc.).

EFDA

Activities in pursuit of the EFDA objectivesI- Co-ordinated activities of the Associations for research, and for the development and exploitation of common tools or facilities/devices;

II- Collective use of the JET facilities

III- Training and carrier development of researchers, promoting links to universities and carrying out support actions for the benefit of the fusion programme

IV- Providing a framework for coordinating European contributions to international collaborations

In all the EFDA activities, specific effort will be devoted to integrate the new Member States/Associations into the EFDA programme.

EFDA

Co-ordinated activities of the Associations for research, and for the development and exploitation of common tools or facilities/devices;

joint scientific exploitation of major fusion devices, that will be promoted, in view of achieving the objectives of the EFDA Workplan, and encouraged by the provision of appropriate incentives and framework;the co-ordination of common tools developed under the EFDA Workprogrammes;the co-ordination of R&D activities requested by the Joint Undertaking Fusion for Energy, which might include physics R&D conducted in Associations and/or under international collaboration;the development of quality assurance standards and procedures, remote participation tools, common engineering modelling tools and standards, etc. in the Associations;the coordination of relevant data bases.The activities will be carried out in pursuance of the EFDA programmatic objectives and in view of an efficient participation of the Associations in ITER construction and exploitation and in preparation of DEMO.Task Forces and Topical Groups will be set up as needed to support the EFDA Leadership in the implementation of these actions.EFDA will also be in charge of identifying the need for urgent development of facilities in support of the objectives of the Workplan and of recommending on resource allocation.

Training a new generation of physicists and engineers:

- 200 staff to be trained over the coming 5 years under training projects

- new Fusion research grants: competition will be open to all post-docs in European Labs / ~10 grants per year

Content of the talk

Fusion strategy

ITER: a major Step

Accompanying programme

IFMIF and Materials R&D

Organisation of the European programme

Involvement of the Portuguese Association

Participation of IST staff in EFDA JET Work Programme 2006IST

IST staff involved in the EFDA JET Work Programme 2006

StaffSummary of staff roleTask ForceD. AlvesKS9 operationD, MP. BeloControl Room MHD Expert, Code Development, ModellingM, S1, T, EJ. BizarroModellingS2D. BorbaScientific CoordinatorMR. CoelhoData Analysis, Scientific CoordinatorMS. CortesScientific Coordinator, MSE data analysisS2A. ElfimovScientific CoordinatorMH.FernandesDJ. FerreiraCode development, modellingTA.FigueiredoHA. FonsecaMicrowave D

StaffSummary of staff roleTask ForceS. HacquinData Analysis, Diagnostic CoordinatorM, S2, DL. MenesesOperation of KG8DF. NabaisScientific Coordinator, MHD ExpertT, H, MM.F.F.NaveScientific Coordinator , Session Leader, Control Room MHD Expert, data analysisM, H, S2I. NedzelskiOperation of KY6DA. NetoDI. NunesScientific Coordinator, Session LeaderS1R.C.PereiraDV.V. PlyusninScientific Coordinator, Disruption and runaway expertE, M, S2T. RibeiroEC. SilvaSOL physics expert, KY3 probe operationEA.VannucciData analysisM

Main areas of involvement Fast ion losses associated with MHD modes Resonance Condition for Alfvn Cascades Excitation X-mode versus O-mode Interferometry/reflectometry measurements of Alfvn Eigenmodes with strong reversed shearAE excitation with ICRH beatwaves Neural network studies to forecast the occurrence of disruptions and ELMs Study of the toroidal plasma rotation braking induced by error-fieldsGiant sawtooth stability and core-localized fluctuations in JET plasmas Using MHD as a diagnostic for rotation The role of double tearing activity in the current density rearrangement scheme in extreme reversed shear JET plasmasMSE analysisCharacterization of the non-thermal properties of the Electron Cyclotron Emission registered during ELMs in high performance plasmasModelling of Advanced Tokamak Scenarios Modelling impurity transportExploration of beam modulation as a tool for viscosity and heat transport measurements Determination of plasma rotation in JET discharges with low momentum inputQuasi Double Null identify experiments for JET and AUGPower exhaust studies in MKII-HD ELMy H modesTritium recovery and runaway suppression with gas terminations in high current plasmasMitigation of disruptions DMVCommissioning of new/upgraded diagnostics/systems

Some Highlights

Scenario with tolerable ELMs in JET (1)Quasi Double Null identify experiments for JET and AUG(I. Nunes) JET parameters: Ip = 0.86 MA, BT = 1.1 T, ne,ped = 2.5x1019 m-3, Te,ped = 0.6 KevJETAUGJET shape scaledto match as much as possible the AUGone

Scenario with tolerable ELMs in JET (2)Study of Type II ELM regime as an alternative for ITER with acceptable ELM sizeSteady state regime with Type II ELMs obtained with 5% temperature drop, H98(y,2) 0.9 Necessity of quasi double null configuration confirmedType II ELMs also observed at Ip = 1.2 and 1.6 MA (reduced *)However, density scans show that operational space for Type II ELMs at Ip values above is narrow, ne,ped/nG 0.7 - 0.8, and lowest * 0.3Operational space of Type II ELMs(I. Nunes)

X-mode reflectometry measurements of Alfvn EigenmodesFirst ever simultaneous measurement of radial location and time-frequency of Alfvn Cascades (S. Hacquin)ACsTAEsACsAt t 6.5 s

ACs appearing on 85 GHz channel but disappearing on 92 GHz channel => RAC 3.3 m Before t 6.5 s

TAEs mainly on 85 GHz => RTAE 3.35 m Spatial and temporal evolution of qmin(R,t) obtainable Important for the development of advanced scenarios

Toroidal rotation in Ohmic and RF heated plasmasBoth co- and counter-rotating profiles are observed in RF heated plasmasOhmic Plasmas are counter-rotatingNBI plasmas are co-rotating Determine direction of rotation in JET diverted plasmas Establish under which conditions co- and counter-current rotation arises in JET RF heated plasmas (F. Nave)CXRS Toroidal Angular Frequency Profiles for similardischarges, red (1st reliable profile after blip starts), blue (atthe end of blip).

Modelling ITB plasmasIt is shown that relaxation oscillations associated with repetitive ITB buildup and collapse in high-performance tokamak plasmas with ICRH, NBI, and LHCD anda dominant fraction of bootstrap current can be overcome if the LHCD power is sufficientlyhighControlling ITB Oscillations in High-Performance Plasmas with a Dominant Fraction of Bootstrap Current (JPS Bizarro)

Redistribution of ICRH Fast Ions Typical losses for TAE+ Precessional / Hybrid FishbonesTypical losses for TAE+ Tornados + Diamagnetic FishbonesBefore TornadosAfter TornadosDuring Sawtoth CrashFast ion losses associated with MHD activity and sawtooth crashes were successfully measured (F Nabais)

Modelling of impurity transport Simulations with COCONUT have confirmed previous results that D gas puffing helps avoiding radiative collapseELMs are an important factor for an effective removal of impurities from the ETB and main SOL to the divertor regionTIMECore Neon Concentration [%]Numerical simulations of recycling impurity screening on JET(P Belo) 3 Deuterium puff levelsCore Neon Concentration for three deuterium puff levels; H-mode plasmas with (continuous line) and without ELMs (shaded line)

Radial correlation reflectometry in JET Recent correlation reflectometry measurements in JET show a clear decrease of the radial correlation length in the region inside the ITB foot, which is compatible with a reduction of turbulence in the plasma coreCorrelation reflectometry in plasmas with ITB (A.Figueiredo)

Involvement of IST in the Technology Workprogrammes

Summary of IST Tasks

TechnologyYearTasksDesign Support20061Site and Plant Layout20071Enhancement Programme2002-20043Diagnostic Systems2000-20066Operation20051Plasma Edge2004-20062Licensing20001Advanced Materials2000-20033Helium Cooled Pebble Bed2001-20044Structural Materials2001-20056Assembly Procedure20001

Tritium Breeding and MaterialsCeramic breedersCompatibility of ceramic breeders (Li4SiO4 and Li2TiO3) with structural (EUROFER and SiC) and cladding materials used in irradiation tests

Beryllium pebble bedsMeasurement of the electrical resistivity of beryllium pebble beds under different mechanical loads and temperatures and in presence of DEMO relevant purge gas (He + 0.1% H2)

Study of the impurity distribution and oxide scale of the pebbles before and after the resistivity measurements

Beryllium-Titanium alloysCharacterization of Be12Ti pellets ( 8 mm diameter, 2 mm thickness) to assess surface and internal chemical composition, oxide layer thickness, presence of secondary phases.R&D on materials to be used in the European design of DEMO Breeding Blankets

Characterization of Be-Ti alloysBeryllides impurity analysisThe same characterisation will be carried out on Be12Ti alloy samples manufactured in the EUIn the frame of the R&D for the optimisation of the neutron multiplier for the solid breeder (HCPB) blanket, two Be-Ti alloys provided by JAERI were characterised OxidationThe oxidation of neutron multipliers in the HCPB design is an important safety issue (exothermal reaction between Be and air/steam)Oxidation behaviour of Be-Ti samples (Be-5%Ti) at various temperatures (600-800oC) in dry air has been investigated.RBS oxygen profiles were measured in regions of the same sample but with Ti-depleted or Ti-rich (Be12Ti) phasesIn the region with Be12Ti (Ti-rich phase) oxidation is reduced as shown by the curves in the two graphsX-ray diffractometry phase composition

ElementConcentration Be5at%TiConcentration Be7at%TiCr11550Mn16599Fe740300Ni17046Cu8015Zn10-Zr12040U20060

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft

FZK EURATOM ASSOCIATION

FUSION

TW4-TTBB-005 D5BeTi compounds from JAERIImpurity analysis

Be-7at%Ti concentration maps

Ti

Cr

Fe

Characterisation of structural materials Structural materials

SiC/SiC compositesdetailed measurement of the impurities content Thermophysical properties and materials characterisationCompatibility: characterisation of corroded surfaces and impurities mapping

Reduced Activation Ferritic-Martensitic steelsMetallurgical, mechanical and chemical characterisation of the EU ODS-EUROFER steel by TEM and XRD analysis.Correlation between microscopic characteristics and macroscopic (mechanical) propertiesCorrosion testsFront surface and cross section of three SiC/SiC composite samples produced by Polymer Impregnation and Pyrolysis

Analysis of impurity and elemental distribution in SiC/SiCSurface analysis of sample A by PIXE (Particle Induced X-ray Emission) and SEM (Scanning Electron Microscopy) revealed low content of Ca, K, Ti, Fe, Zn, Cu and Ba, while O was not detectedLower impurity contents are required in the under development EU-referenceElements are not uniformly distributed as shown in the more detailed SEM picturesElemental distribution maps by SEM

Diagnostics for ITER

Secondment to the ITER IT (Visiting Researcher or VHTP) for support in the diagnostic area by Dr. A. Malaquias (2000-2003) Important contributions in particular on: design of CXRS and MSE systems (including optical design and assessment polarization effects on first metallic mirrors) and integration of various diagnostics into port plugs (including the preparation for a DCR for a reallocation of ports).

Plasma-position reflectometry Coordinated by Prof. M.E. Manso and Dr. P. Varela Preparatory study of the system Lead Association of a Cluster of Associations for the drawing up of a Project Plan for the full development of the diagnostic and advancement of the design in critical areas Collaboration with the Kurchatov Institute on a mock-up for testing and developing the high-field side waveguide and antenna for the ITER reflectometer systems

Other diagnosticsContributions to other Clusters of Associations for the development of ITER diagnostics, in particular in the area of data acquisition and CODAC: visible/IR wide-angle viewing cameras and core-plasma LIDAR

Plasma-position reflectometry (examples from Contract EFDA 03-1118)Review of plasma-position reflectometerEngineering assessment, e.g. thermal assessment of antenna; see belowDesign (e.g. waveguide routing, consequences from engineering assessment)Various simulations, such as waveguide transmission losses (see below) and antenna performance (e.g. the effect of an asymmetric construction on radiation patterns)

Participation of Portuguese Association on Plasma Edge Technology Programme (I)TW4-TPP-ERCAR: High fluence modifications of carbon PFCPISCES-BNo grass-like structure in tokamaks for fluences ~ 1026 m-2Carbon PFCs subject to large fluences in plasma simulators suffer large surface structure modifications (decrease of Ychem) Potential problem for ITER because of poor power handling Tokamak PFC analysisASDEX Upgrade Div IIb Measurements by AFM in ITNTokamak plasmas smooth surfaces in erosion zones surface roughness similar to virgin tiles in deposition zonesInvolvement of ITN in surface analysis of samples exposed to tokamaks

Participation of Portuguese Association on Plasma Edge Technology Programme (II)TW6-TPP-ERDEP: Material erosion and fuel retention for ITER-relevant divertor target surface temperatures , plasma impact energies and compositionInvolvement of ITN in surface analysis of samples exposed to plasma simulators in ITER-like conditions CFC erosion and fuel trapping under plasma impact (1021-1024 m-2s-1)(D+He+Ne/Ar) with Te ~ 1 -10 eV & Tsurf ~ 400 1000 oC PSI-2 & Pilot-PSI W erosion and fuel trapping under plasma impact (1021-1024 m-2s-1) with Te ~ 1 -10 eV, Tsurf ~ 400 1000 oC & nC/ne = 0.1 10% PSI-2 & Pilot-PSI ITN will carry out surface analysis studies to determine : Fuel retention in surface layers for the targets exposed to plasma simulators Surface modifications associated with exposure to plasma (W/C compound formation and possible enhancement of blistering)

Portuguese Contribution to EU ITER Licensing Working Group Objective of the Working Group:Assessment of the ITER-JCT safety approach by the EU Licensing Working Group (LWG)

Main result of the Working Group:There is no fundamental bar to licensing ITER in any of the countries which participated in the study (i.e., Belgium, France, Germany, Spain, Portugal, United Kingdom)

IST Contract on QANew activity QA Support in the Development of the QA System for the ITER EU Domestic Agency and Implementation of a Quality Assurance Programme in the European Fusion Associations for ITER-relevant Activities.Expertise for the contract provided by the Instituto de Soldadura e Qualidade (ISQ);Deliverables: Presentation to Associations of a case study based on relevant R&D or manufacturing task: ISQ QA support to CERN LHC project; Assistance to a specific Association (FZK) in developing and implementing a Quality Plan for an EFDA WP2007 technology activity (HCPB: Test Blanket Modules design and integration analysis) on the basis of existing EFDA/ELE QA principles; Inventory of available Standards and Level 3 documents (Specifications for the work, codes of practice, internal standard, etc.) available in the EU Fusion community to prepare a on-line Library.

CONCLUSION

New horizons for Fusion Reserach

ITER

Strong Accompanying Programme including JET with ITER-like wall experiment in preparation and a unique DT capability until ITER startsJT60SA: upgrade of JT60U jointly conducted by EU and Japan

IFMIF starting final design and engineering validation phase

New Organisation of the European programme

Involvement of the Portuguese Association: strong and of high quality / further developments are welcome

What is PF system?What is PF system?