R

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RD priorities for the fusion programmeand
contributions from EFDAJerome PAMELA, EFDA
Leader
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• 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.
• gt power plant-oriented strategy
• gt key steps in this strategy ITER and DEMO
• gt Fast Track approach
• DEMO single step after ITER
• IFMIF (materials test facility) operating in
  parallel to
• ITER

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Strategy towards DEMO and Power Plants
TECHNOLOGY PROGRAMME
ITER
DEMO
POWER PLANT
PHYSICS PROGRAMME
Alternative Concepts (Stellarator)
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Gap Analysis presented to the Facilities Review
(2008)
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What we expect from ITER

• The scientific demonstration of fusion a Burning
  Plasma at Q10
• Development of long pulse/steady state modes of
  plasma operation (with a target of power
  amplification Q5)
• 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

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CORE PROGRAMME (1/2) As recommended by the
Facilities Review Panel (October 2008)
During the period of ITER construction the key
strategic RD emphasis should be on A1)
Supporting ITER construction and preparation for
operation specifically by Accomplishing
outstanding RD issues and exploiting recent RD
progress for the 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 the rapid start-up of ITER, targeting
promising operational regimes Strengthening
diagnostic and modelling capabilities and
fostering developments for improved solutions in
specific areas of fusion physics and
technology. A2) Preparing DEMO design,
simultaneously carrying out long lead RD by
Strengthening a coherent materials research
programme for DEMO and future fusion power plants
and establishing experimental means for
validation Advancing Tokamak concept
improvements and pursuing the Stellarator line
for optimizing the path towards DEMO and a
commercial fusion power plant Establishing
soon a group for proceeding towards the
definition of a conceptual DEMO design, steering
the DEMO RD programme and preparing
industrial involvement.
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CORE PROGRAMME (2/2) 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 RD, with
increased involvement of industry and utilities,
by focusing on Achieving the goals of ITER in
DEMO relevant conditions with emphasis
on steady-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 the Stellarator for optimizing the
path towards commercial fusion power
Developing a numerical burning plasma device
for the detailed prediction of fusion 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
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RD in support to ITER
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Technology RD in relation to ITER

• Activities in direct support to construction
  (qualification of techniques, prototypes)
  magnets (including cold tests), vacuum-vessel,
  blankets, divertor, T-plant etc.
• Technically demanding Areas, where RD in
  laboratories will be needed either on the short
  mid-term (activities linked to construction) or
  on the longer 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)

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Example Extracts from ITER RD plan shown at
ITER-STAC, May 2009
RD Items and Plan in Divertor
Last PA issue date Dec 2009 for PFC, July 2010
Cassette body
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Physics RD 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

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Physics RD 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)

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RD in preparation of DEMOtechnology and physics
Preambulum The Core Programme as recommended by
the Facilities Review Panel would require
resources that are not going to be available for
several years. Financial constraints will most
likely impact the schedule of DEMO activities. A
DEMO advisory group will make proposals at
CCE-FU/F4E by the turn of the year 2009/10.
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Gap Analysis presented to the Facilities Review
(2008)
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Materials Activation by fusion neutrons a
specific problem
14 MeV neutrons from DT reactions He generation
rate higher than from fission (slower) neutrons
IFMIF
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Requires a specific facility (IFMIF) and a
significant RD programme
Fusion
He generation (appm/year)
200
ITER
Fission
0
0
20
40
Displacement damage (dpa/year)
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Main priorities in other technologies(from ITER
to DEMO/non-exhaustive list)

• Heating and Current Drive
• Improve efficiency and reliability
• Power plant control and diagnostics
• Comply with very tough limitations due to harsh
  environment
• Remote Handling
• concepts to optimise plant availability
• Reactor grade plasma facing components and
  divertor
• Develop high temperature tungsten divertor
• Explore alternative divertor concepts
  technologies
• Tritium self-sufficiency
• Breeding Blanket programme complementing the ITER
  Test Blanket Module programme
• Extraction of T at high through-put

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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

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Physics and Plasma Operation The Step Ladder
Approach to ITER and from ITER to DEMO
Similarly extrapolation to DEMO will require a
set of tokamaks spanning a broad range of physics
parameters to validate the Tokamak Simulator 1-2
MA class 5 MA class 15 MA class (ITER)
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(No Transcript)
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Mid-size devices (1-2MA class)

• Large tokamaks (4-6MA class)
• / ITER satellites
• JET on the mid-term
• JT60SA and a European Satellite
• (FAST is a possible example)
• on the long term

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• Towards DEMO/ Power plants
• Alternative magnetic confinement concepts

• Stellarator as an inherently steady state
  disruption free device (1 generation behind
  tokamak but relevance recognised by Facilities
  Review).
• W7X
• Confirmation of expected Stellarator benefits
• Validation of fully validated Stellarator
  Simulator

Spherical Tokamak as an option for a Component
Test Facility and in support to ITER physics
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EFDA Contribution
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EFDA
All EU Laboratories/Institutions working on
Fusion are parties to EFDA

• Collective use of JET
• Reinforced coordination of physics and technology
  in EU laboratories
• Training
• EU contributions to international collaborations
  outside F4E

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JET
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JET ITER-like wall experiment

• 700m2 Beryllium first wall
• low Z
• Oxygen getter
• Optimise plasma performance
• But large erosion melting

ITER

• 100m2 Tungsten
• Low erosion
• high melting T
• Negligible T retention
• Optimise lifetime T- retention
• But high Z melting

JET

• 50 m2 Graphite CFC
• Lowish Z
• No melting in transients
• Superior heat shock behaviour
• Optimise heat flux resistance
• But large erosion T retention

Shutdown for installation started 26 Oct. 2009
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JET retains its DT capability
fast alphas from DT reactions on JET
Further key DT contributions would be possible in
support to ITER - study of tritium retention
with all metallic walls- isotopic effects in
ITER-relevant plasma scenarios and physics-
confirmation of ITER scenarios with the same
combination of wall materials and DT fuel-
burning plasma physicsPlanning for JET
including possible DT experiment requested by the
EFDA steering Committee
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Coordination of RD in Associations EFDA Task
Forces Topical Groups
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Coordination of RD in Associations EFDA 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 (EC), G.Falchetto (CEA) Topical
Groups under EFDA Transport Topical Group
Chairman C.Hidalgo (CIEMAT) HCD Topical Group
Chairman A.Becoulet (CEA) Materials Topical
Group Chairmen S.Dudarev (UKAEA) M.
Reith (FZK) Diagnostics Topical Group Chairman
T.Donné (FOM) MHD Topical Group Chairman
P.Martin (ENEA-RFX)
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EFDA 2010 Work Programme / Overview
gt Longer term vision gt Focus along the seven
RD Missions proposed by EFDA and endorsed by the
Facilities Review Panel

• Burning Plasmas
• Reliable Tokamak Operation
• First wall materials compatibility with
  ITER/DEMO relevant plasmas
• Technology and physics of Long Pulse Steady
  State
• Predicting fusion performance
• Materials and Components for Nuclear Operation
• 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
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Burning Plasmas
Mission I
Priority support is directed to the measurements
of fusion products and related diagnostics
Confined alphas measurements
Lost alphas measurements
Neutronics
RISO
Design of neutron spectrometer (ENEA)
Fuel ion ratio
TEXTOR (FZJ)
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.
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Reliable Tokamak Operation
Mission II
Priority 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.
Radiation during Mass Gas Injection (CRPP)
MAST filaments (UKAEA)
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.
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First wall materials compatibility with
ITER/DEMO relevant plasmas
Mission III
Priority support on the development of
thermography for metallic walls, a key issue for
JET and ITER.
JET
Tore Supra (CEA)
Diagnostics hardware for development of
Thermography for Metallic Walls and co-ordinated
experiments on mitigation and control of heat
loads.
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Technology and physics of Long Pulse Steady
State (I)
Mission IV
Priority support focused on the EU contribution
to the development of LHCD for ITER, improved NB
technologies and development fast wave off-axis
current drive.
LHCD Antenna (CEA)

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

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Technology and physics of Long Pulse Steady
State (II)
Mission IV
Priority support for the development of new
diagnostic concepts and analysis techniques,
including further development of plasma position
control in long pulse operation.

• 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.

non-magnetic plasma position diagnostic (ENEA)
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Predicting fusion performance (I)
Mission V
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).

• 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.

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Predicting fusion performance (II)
Mission V
Integrated Tokamak Modelling, priority support is
focused on coordination activities,
standardization towards joint tools, structures
and formats, and the ETS.
ITM Workflow in Kelper
ITM Gateway in Portici (ENEA)

• 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
  VV efforts of these modules.

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HPC-FF High Performance Computer for Fusion
Applications

• Located in the Jülich Supercomputing Centre

• 1080 computer nodes
• Bull NovaScale R422-E2
• 20 racks with 54 nodes each
• Processor Intel Xeon X5570 (Nehalem-EP)
  quad-core,
• 2.93 GHz
• Memory 250 TB

• Peak theoretical performance 100 TFlop/s
• Operating since 5 August 2009

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Materials and Components for Nuclear Operation (I)
Mission VI
Development of ground-breaking advanced tools for
Radiation Effects Modelling and Experimental
Validation in EUROFER as 1st Priority
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).
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Materials and Components for Nuclear Operation
(II)
Mission VI
Optimise the conditions for Nano-Structuring ODS
Ferritic Steels fabrication at the
semi-industrial scale and characterisation
ODS Should Mitigate Inter-granular Embrittlement
and Swelling
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Materials and Components for Nuclear Operation
(III)
Mission VI
Develop Heat Resistant and Oxidation Resistant
W-alloys Priority Support focused on Fabrication
of new alloys and their joint characterisation
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Other/new coordinated activities

• Fuelling (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, HCD for DEMO,
  radiation
• Superconductors for fusion applications aim at
  demonstration coils in 3 years (MgB2) / 6 years
  (YBCO)

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Socio-Economic Research on Fusion (SERF)

• 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)
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Public Information

• Fusion Expo
• EFDA Newsletter
• European Public Information Group
• PI materials
• visits at JET
• Participation in Eiroforum

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TRAINING UNDER EFDA
Goal Oriented Training Programme
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 gt develop a brand
of excellence
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Summary