The European fusion research programme aims at developing fusion as an energy source , i.e

Bucarest, 26-27 November 2009Presentation on fusion R&D priorities and EFDA, B. Weyssow

R&D priorities for the fusion programmeand contributions from EFDA

on behalf of J. Pamela, EFDA Leader

Presented by B. WeyssowEFDA RO

H&CD and FuellingTransport

Remarks, comments, requests: [email protected]


The European fusion research programme aims at developing fusion as an energy source,

i.e. developing the knowledge in physics, technology and

engineering required to design and build fusion power plants.

=> power plant-oriented strategy=> key steps in this strategy: ITER and DEMO=> ‘Fast Track’ approach: DEMO = single step after ITER IFMIF (materials test facility) operating

in parallel to ITER


Strategy towards DEMO and Power Plants

ITERITER DEMODEMO

PHYSICS PROGRAMMEPHYSICS PROGRAMME

POWER PLANTPOWER PLANT

TECHNOLOGY PROGRAMMETECHNOLOGY PROGRAMME

Alternative Concepts (Stellarator)Alternative Concepts (Stellarator)


4

Gap Analysis presented to the Facilities Review (2008)

DEMO Phase 1 and phase 2: different sets of blankets


What we expect from ITER• The scientific demonstration of fusion: a Burning Plasma at

Q=10 • Development of long pulse/steady state modes of plasma

operation (with a target of power amplification Q=5)• Functional tests and test under neutrons of Test Blanket

Modules (tritium breeding)• Demonstration of a number of key components close to

power plant requirements (magnets, vessel, T plant, safety, etc)

a key input to support the launch of DEMO construction in about 20-25 years

a necessary input, which however needs to be complemented by a significant accompanying programme in technology and physics


During the period of ITER construction the key strategic R&D emphasis should be on

A1) Supporting ITER construction and preparation for operation• Design and construction of ITER systems and components • Resolving ITER physics issues which might limit the performance, constrain the accessible parameter space and/or impact on the operational reliability;• Preparing rapid start-up of ITER targeting promising operational regimes;• Strengthening diagnostic and modelling capabilities and fostering developments for improved solutions.A2) Preparing DEMO design, simultaneously carrying out long lead R&D by• Strengthening the materials research programme for DEMO and futurefusion power plants and establishing experimental means for validation;• Advancing Tokamak and Stellarator concepts for optimizing the path towards DEMO and a commercial fusion power plant;• Establishing a DEMO group for proceeding towards the definition of a conceptualDEMO design, steering the DEMO R&D programme and preparing industrialinvolvement.

CORE PROGRAMME (1/2)As recommended by the Facilities Review Panel (October 2008)


During the following decade the focus must shift towards

B) Preparing for DEMO construction, based on ITER and the accompanying R&D, with increased involvement of industry and utilities, by focusing on• Achieving the goals of ITER in DEMO relevant conditions with emphasis onsteady-state aspects;• Developing a blanket and auxiliary systems compliant with DEMO conditions;• Optimising and validating suitable materials and components for DEMO;• Assessing concept improvements for the Tokamak and the potential of theStellarator for optimizing the path towards commercial fusion power;• Developing a “numerical burning plasma device” for the detailed prediction offusion performance and assistance in the definition and design of DEMO;• Establishing the engineering design for DEMO.

These ITER and DEMO priorities must be complemented by

C) Pursuing innovation

D) Maintaining and renewing the staffing basis of the Programme

CORE PROGRAMME (2/2)As recommended by the Facilities Review Panel (October 2008)


R&D in support to ITER


Technology R&D in relation to ITERActivities in direct support to construction (qualification of techniques, prototypes): magnets (including cold tests), vacuum-vessel, blankets, divertor, T-plant etc.

R&D in laboratories will be needed short & mid-term =activities linked to constructionlong term = activities linked to the ITER experimental programme- Plasma Facing Elements (First Wall: Be short term; Divertor: W mid-term)- Dust and Tritium removal technologies (mid-term)- Fuelling and pumping technologies (mid-term)- In-vessel coils (mid-term)- Tritium Breeding Blanket (mid and longer-term):

- Preparation of Test Blanket Modules (structural and functional materials, Tritium extraction technique, joining and other manufacturing technologies)

- Tritium Plant (mid-term)- Remote handling (mid-term)- Heating and current drive techniques (mid and longer-term)

- Neutral beam sources and accelerators- Gyrotrons (possibly 2 MW units) - Lower hybrid couplers (test of ITER-relevant coupler on tokamak)


Physics R&D in support of ITER(support to construction and preparation of operation)

- Preparation for burning plasma experiments- Fast particle physics- Burn control - Diagnostics for burning plasma

- Minimisation of fuel retention - Plasma wall interaction (Physics of erosion, codeposition, T-

retention in W and Be)- Diagnostic techniques (T-retention, Dust etc.)

- Control of MHD- Plasma performance: NTMs, RWMs - Limitation of transient heat loads: ELMs (among the highest

priorities)- Reliable operation: Disruption avoidance and mitigation


Physics R&D in relation to ITER

- Optimisation of plasma operation with metallic plasma facing materials (full W divertor)

- Development of plasma scenarios for long pulse / steady state

- Current Drive physics- Improved H-mode- Advanced modes with extensive current profile control

- Transport and Confinement Physics- H-mode and Edge Pedestal- Turbulent transport

- Integrated Modelling - Progress on first principles physics codes / validation against

experiments- Common framework and tools for integrated modelling (interpretative

and predictive)


Physics from ITER to DEMO

- Fully validated ‘tokamak simulator’

- Very robust plasma scenarios, compatible with control capabilities (limited set of diagnostics and actuators; balance between performance and reliability)

- Highly radiative plasma scenarios

- Very long pulse operation


EFDA Contribution


• Collective use of JET

•Reinforced coordination of physics and technology in EU laboratories

• Training

•EU contributions to international collaborations outside F4E

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

EFDA


JETPresented by Dr. Romanelli

EFDA Associate Leader


Coordination of R&D in Associations:

EFDA Task Forces & Topical Groups

First Call for Participation EFDA WP2010 TG HCD, Diag, MHD, Transport now closed


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 (EC), G.Falchetto (CEA)

Topical Groups under EFDA

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

Transport Topical Group: Chairman C.Hidalgo (CIEMAT)

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

Diagnostics Topical Group: Chairman T.Donné (FOM)

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

Coordination of R&D in Associations: EFDA Task Forces & Topical Groups


Exemple of coordinated activity: Task WP08-HCD-03-01

Midterm ProgressCoordinator: Tuong Hoang

For: J.F. Artaud, A. Bécoulet, J.H. Belo, G. Berger-By, J.M. Bernard, Ph. Cara, A. Cardinali, C. Castaldo, S. Ceccuzzi, R. Cesario, J. Decker, L. Delpech, A. Ekedahl, J.Garcia, P. Garibaldi, G. Giruzzi, M. Goniche, D. Guilhem, J. Hillairet, G. T. Hoang, J. Hua, Q.Y. Huang, F. Imbeaux, F. Kazarian, S.H. Kim, X. Litaudon, R. Maggiora, R. Magne, L. Marfisi, S. Meschino, D. Milenasio, F. Mirizzi, L. Pajewski, L. Panaccione, Y. Peysson, G. Schettini, P.K. Sharma, M. Schneider, A. Tuccillo, O. Tudisco, G. Vecchi, S. R. Vilari, K. Vulliez


TASK WP08-HCD-03-01 ‘LH4IT’, following the ITER STAC recommendation

Providing a pre-design document including the conceptual design, costing, possible procurement allocation, WBS, R&D needs CEA, ENEA, IST, POLITO, Univ. ROME 3 (> 4ppys)Collaboration with IO- HCD Department (Integration aspect) and the International Fusion community: China, India, Korea, US and Japan (follow-up only)

Training program LITE (7 trainees): 4 trainees on LHFocusing on RF/mechanical aspects of the IC and LH systems (whole system, from the source to the antenna)

Validation of PAM concept at Tore Supra with EU and non EU partners

LH PROGRAM IN RUN UNDER EFDA


ITER LH System: WBS

Physics design

Launcher conceptual design

Transmission lines

Integration

Working groupsPhysicsLauncherT-linesPower SupplyControl & Protection DiagnosticsIntegration

LITE

Done or on-going


ITER LH System: Physics Modeling

What has been done?

Optimize the N// range by performing integrated simulations of propagation / absorption in ITER various design scenarios (SS, Hybrid, ramp-up phase and baseline) in varying ne, Te, and poloidal position

Choice of location in ITER to avoid magnetic connection (coupling issue)

Alpha absorption issueLH current and deposition vs N//

Scenario 4

Propagating region for N//= 2


What has been done?

Retrieve results of DDD2001 (with various codes). Update the heat fluxes

Modify the DDD2001 design to

Improve the N// flexibility, power density,

Optimize the directivity, RF hardware (phase shifters, bi-junction)

Thermo-mechanical analysis. Study different options for the Be front face

Initiate the design of a Fully Active MJ for a back-up solution (RF design, thermal analysis)

ITER LH System: Launcher

Optimizing bi-junctions

DDD2001


Antenna Front Face

4 different models have been studied:

- DDD2001 PAM model

- 2 Alternative PAM models “Case A” and “Case B”

- FAM, alternative concept to the PAM

Case A

Case B

DDD2001

FAM


Port # 11Klystrons

ITER LH System: Transmission-lines

What has been done? Revise the DDD2001 strongly

Reduce the number of TLs (klystron 1MW in DDD2001; 500kW now)

Integration in ITER environment Design of RF windows (on-going)

48 RF Windows


ITER LH System: Power Supply & Control & Protection

What has been done?

Characterize Power Supply requirements and conceptual design

(HVDC PS based on PSM, pulse step modulator, technology)

Characterize specific diagnostics

RF measurements: Power and phase control and safety interlocks

Window arc detection: Optical fibers compatible with ITER

environment

Density measurement at grill mouth: Front face reflectometer

Diagnostic viewing the antenna front for detecting arcs: IR/VIS

cameras, bolometry. Location of diagnostics with respect to the LH

antenna


EFDA 2010 Work Programme / Overview

=> Longer term vision

=> Focus along the seven R&D Missions proposed by EFDA and endorsed by the Facilities Review Panel

I. Burning Plasmas II. Reliable Tokamak Operation III. First wall materials & compatibility with ITER/DEMO relevant plasmas IV. Technology and physics of Long Pulse & Steady State V. Predicting fusion performance VI. Materials and Components for Nuclear Operation VII. DEMO Integrated Design: towards high availability and efficient electricity

production.

The programme priorities take into account the ITER research plan, activities conducted under F4E and the outcome of ITPA


Burning PlasmasPriority support is directed to the measurements of fusion products and related diagnostics

Confined alphas measurements Neutronics

Fuel ion ratio

Lost alphas measurements

Design of neutron spectrometer

(ENEA)

RISO

Mission IMission I

Diagnostics hardware for improved measurements of confined and lost alphas, neutrons and fuel ion ratio in support of diagnostic developments for ITER and physics studies in present machines and for co-ordinated experiments.

TEXTOR (FZJ)


Reliable Tokamak OperationPriority support is focused on Disruptions studies and ELM mitigation, with a specific emphasis on high-Z materials for the Plasma Wall interaction aspects, and on Dust & Tritium emerging technologies for possible application on ITER.

Before (1.300 s), during (1.305 s) and after (1.310 s) the injection.

Unfiltered diodes

Radiation during Mass Gas Injection (CRPP) MAST : filaments (UKAEA)

Mission IIMission II

Specific software developments for linear/non-linear MHD studies including 3D geometry and kinetic effects. Co-ordinated experiments on mitigation and control of MHD instabilities. Diagnostics for improved measurements of runway electron beam and impurity dynamics, halo currents and vessel forces.


First wall materials & compatibility with ITER/DEMO relevant plasmas

Priority support on the development of thermography for metallic walls, a key issue for JET and ITER.

JET

LH ICRH : fast e-

Tore Supra (CEA)

Mission IIIMission III

Diagnostics hardware for development of Thermography for Metallic Walls and co-ordinated experiments on mitigation and control of heat loads.


Technology and physics of Long Pulse & Steady State (I)

General H&CD and Fuelling physics and Technology: Cadarache 8-11 february 2010

LHCD Antenna (CEA)

Mission IVMission IV

-EU contribution to the LHCD for ITER development plan: coordination; diagnostics, conceptual design; source, transmission lines and antenna.

-Developments Neutral Beam Advanced Technologies: co-ordination, conceptual designs and modelling of sources, accelerator techniques and alternative neutraliser technology.NB-CC meeting: Garching 24-26 november 2009

- Fast wave off-axis current drive physics, antenna modelling, power sources and co-ordination.


Technology and physics of Long Pulse & Steady State (II)

Priority support for the development of new diagnostic concepts and analysis techniques, including further development of plasma position control in long pulse operation.

non-magnetic plasma position diagnostic (ENEA)

Mission IVMission IV

-Development of plasma position control in long pulse operation; implementation and tests in present machines.

-Development of new diagnostic concepts and analysis techniques, implementation and tests in present machines.

-Development of data analysis, validation, calibration and real time techniques; implementation and tests in present machines.

- Co-ordinated experiments.


Predicting fusion performance (I)Priority support focused on detailed studies of the L-H transition and plasma pedestal properties, including the development of better diagnostics; and on electron transport studies (dominant electron heating as on ITER).

distance from axis

pre

ssur

e

L-mode

pedestal

H-mode

Mission VMission V

-Diagnostics hardware for improved measurements of key parameters related to L-H transition (Edge Currents, Flows, Neutral densities and Turbulence) in support of detailed physics studies.

-Diagnostics hardware for improved measurements of key parameters related to electron transport, impurity transport, plasma rotation and edge turbulence in support of detailed physics studies

- Co-ordinated experiments.


Predicting fusion performance (II)Integrated Tokamak Modelling, priority support is focused on coordination activities, standardization towards joint tools, structures and formats, and the ETS.

Initialisation

EFIT equilibrium

Refined HELENA equilibrium

MISHKA linear MHD stability

Result to database

ITM Workflow in Kepler ITM Gateway in Portici (ENEA)

Mission VMission V

- Incorporation of new modules and promoting their use in advanced applications. - Developments towards platform enhancements while maintaining a robust production level platform (ISIP)- Continuing development of the ETS with additional modules being incorporated, as well as V&V efforts of these modules.


HPC-FF High Performance Computer for Fusion Applications

•Peak theoretical performance: ~ 100 TFlop/s

Operating since 5 August 2009

•Located in the Jülich Supercomputing Centre

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

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

•Memory: ~250 TB


Materials and Components for Nuclear

Operation (I)Development of ground-breaking advanced tools for Radiation Effects Modelling and Experimental Validation in EUROFER as 1st Priority

Mission VIMission VI

Displaced atoms (green) and vacant lattice sites (red) at the end of the collision phase of displacement cascades created by 5, 10 and 20keV atomic recoils at 600K (UKAEA).


Materials and Components for Nuclear Operation (II)

Optimise the conditions for Nano-Structuring Oxide dispersion strengthened (ODS) Ferritic Steels:fabrication at the semi-industrial scale and characterisation

ODS Should Mitigate Inter-granular Embrittlement and Swelling



Develop Heat Resistant and Oxidation Resistant W-alloys:Priority Support focused on Fabrication of new alloys and their joint characterisation


Materials and Components for Nuclear Operation (III)

W WL10 W26Re

Lo

ss o

f F

rac

ture

T

ou

gh

ne

ss

835 0CInitial

Microstructure Non-Affected

1200 0CUnacceptable

Recrystallisation

Annealing 1 hour

Increase of Fracture Toughness


Other/new coordinated activitiesFuelling (physics &

Technology)• Gas flow in divertor; pumping

rate influence on scenarios; pellet fuelling database; divertor operation

• Tech: New concepts for cryopumps; high speed pellet injection; concepts for fuelling system.

DEMO (Physics and Technology)

• Physics: Stability margins, H&CD for DEMO, radiation

• Superconductors for fusion applications: aim at demonstration coils in 3 years (MgB2) / 6 years (YBCO)


Socio-Economic Research on Fusion (SERF)

in 2100 inWEU

CO2 (ppm)

• Launched in 1997• Objectives revised in 2008 following

recommendations of an EFDA ad hoc group– Multi-disciplinary field, complementing

existing knowledge bases – Economical viability, social

acceptability, societal implications of fusion power

• Major research lines:– Fusion economics: direct, indirect and

external costs of fusion– Fusion in the energy system long-

term energy scenarios– Fusion as a large technical and

complex system– Public opinion, awareness and

acceptance of fusion communication strategy

CO2 (ppm)


Public Information

• Fusion Expo

• EFDA Newsletter

• European Public Information Group

• PI materials

• visits at JET

• Participation in Eiroforum


- Objective: training young physicists and engineers in areas identified as presenting risks of gaps in the coming years

(~40 researchers per year during 5 years)

- projects must be collaborative (at least 3 Associations), oriented towards practical activities, address the priority areas approved at EFDA SC

- training programmes mainly directed toward early stage researchers

TRAINING UNDER EFDA

Fusion Fellowships Programme - up to 10 post-docs per year selected among proposals from Associations

- fellowships awarded according to the sole quality of the applicants and their proposals => develop a brand of excellence

Goal Oriented Training Programme


Summary- The priorities for fusion R&D are clearly set (the Facilities Review

process has been very useful and ITER should guide a significant R&D programme); a strong accompanying programme is needed (and the need is recognised), but financial constraints are likely to be severe over several years

- The coordinated activities under EFDA cover a wide range of physics and technologies issues aiming at supporting ITER and developing fusion energy

=> Further focusing of the future EFDA programme along the 7 R&D Missions

- JET brings key results in preparation of ITER (ICRH, ripple, ELM pacing, plasma scenarios)

=> The JET ITER-like Wall (with a possible DTE2) will be a key experiment worldwide over the coming 5-6 years

- Development of Human Resources is among top EFDA priorities

Documents

The European fusion research programme aims at developing fusion as an energy source , i.e