newsletter
newsletter
Vol 2003 / 1
February 5, 2003

E UROPEAN F USION DEVELOPEMENT AGREEMENT

News
Issued by the EFDA
Close Support Unit
Garching

Contents

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Interview:
Pablo Fernandez Ruiz
page 2
Toroidal Field Model
Coil: Final Tests
page 3
JET:
Coordination of
Tokamak Experiments
page 4Fusion in Europe:
Lithium deposits inCzech Republic
page 5
Asdex-Upgrade /Finnish Delegationfrom Industry
page 6
Fusion in China
page 7
Personalities
page 8

http://www.efda.org

ITER Negotiations: Growing International Interest in Participating
At their seventh Negotiations Meeting on 2nd of December 2002 in Barcelona(Spain) the delegations from Canada, the European Union, Japan and the RussianFederation saw progress on a number of fronts towards the implementation of the ITER
project. Josep Piqué, Spanish Minister of Science and Technology, emphasized theunconditional support of the Spanish Government, regional and local authorities for the
proposal of Vandellòs as a European site for hosting ITER. The final report of the Project
Board on the Co-ordinated Technical Acitivities for ITER was presented. As a very positive development the delegations welcomed expressions of interest in the ITER projectfrom the People’s Republic of China and the Republic of Korea. Discussions are underway with both countries regarding the possible steps to join the ITER Negotiations
process. The eighth Negotiations Meeting will be held in St. Petersburg (RussianFederation) on February 18-19, 2003. (For News from China please see page 5)
TEXTOR Officially Re-opened after Dynamic Ergodic Divertor (DED) Installation
On 6th December 2002 Forschungszentrum Jülich (Germany) inaugurated a development which is unique within the worldwide fusion effort. The Dynamic Ergodic
Divertor (DED) has been installed in the TEXTOR tokamak to improve the control of thefusion process, especially addressing the transport of energy, heat and particles in theplasma boundary. The DED consists of 18 single coils, which are fixed to the inner torus
walls, exactly where the magnetic field lines hit the vessel. The heat fluxes are normally concentrated by the field lines, forming surface hot spots that may withstand damage
only for a limited time before being overheated. The DED coils produce a rotating(dynamic) distortion of the magnetic field, and the closed magnetic field lines are broken up (ergodised) by vortices at the plasma edge. This helps to spread the heat fromthe plasma boundary over a larger surface. Moreover, it will allow for a better control ofenergy and particle transport in the plasma boundary. The principle of the ergodic divertor was experimentally proven for the first time on Tore Supra at the Association
Euratom-CEA Cadarache (France) based on theoretical studies performed at Jülich
and Cadarache in the 1980s. The addition of the dynamic concept of rotating magnetic fields is a pioneer project led by Forschungszentrum Jülich.

EFDA Fusion Newsletter

page 2

Interview“The best image of a strong and efficient programme drives fusion ahead”
EFDA Newsletter (E.N.): Your professional career started in the field of Aeronautics, which
is – together with Energy – one of the 7 main themes of the European Commission’sFP6. Which parallels do you see between these two fields?
Pablo Fernandez Ruiz: Aeronautics and Energy are both fields of considerable importancein the economy of the EU. Aeronautics, since its beginning, and Energy, more recently,
with their sophisticated forms of production, distribution and use, are highly dependent
upon Research and Development for their future. The EU aerospace industry has gained
its competitiveness at the world level by coordinating and integrating national activities.
When it comes to fusion as a component of energy research, the EU is a world leader,thanks to a very well integrated research programme. So I can say that the integration
aspect in both cases has been very positive for assuring that the EU can compete at theworld level. But I also have a wide experience in the field of nuclear fission. This helps me
greatly because the fission world, even though very specific, helps to understand the fieldof fusion in all of its complexity.
E.N.: How do you see the respective roles of fusion and fission in the future energy market?
Pablo Fernandez Ruiz
began his professional
career in the projects office of Construcciones
Aeronauticas (CASA) in
Madrid (Spain) in the areaof structural analysis. He
has also worked in thearea of nuclear fission
fuel. In 1988 he joined theEuropean Commission,
Euratom as Head of
Division. Now he is the
director of Energy in theEuropean Commission’s
Research Department.

Ruiz: At the moment it’s not possible to achieve the Kyoto objectives without nuclear fission.
But it’s important for our future to develop new technologies for fission as well as forfusion, understanding that the two areas are on two different levels of development:
fission being a reality in the generation of energy, and fusion being on the verge of scientific and technological demonstration of its feasibility. Beyond ITER, one further generationof demonstration and prototype devices will be needed before fusion will enter the market.
In the end the objective of research is to offer options for society to choose when theright moment has come. And at that time we must be prepared in fusion. It’s important tohighlight the fact that fusion provides an enormous advantage in relation to security ofsupply of fuels. These are available within the European Union and could contribute to
reduce the enormous dependence of the European Union on external supply of fuels.
E.N.: In which way will you personally support fusion during the next few years?
Ruiz: ITER is an initiative undertaken jointly by the Europeans and other international players, so it is important to recognize that we have to adapt the fusion programme to the newconditions. I will strongly support the fusion programme in implementing this process, sothat it can reorganize itself to ensure that it is a coherent and well structured programme,
remaining a good model of the European Research Area. This means I will help to findproper support to drive forward the ITER development in the coming 10 years andbeyond. All parties must be involved and we need to present the fusion programme so as
to reflect its true value, as a vital element of the Commission’s energy research programme.
E.N.: In the 2001 proposal by the Commission, fusion was allocated 700 Million Euro.
Eventually, the EU parliament and the Council of Ministers have pushed it to 750 Million
Euro. By “vital element”, do you mean that fusion will get more financial support fromthe Commission during FP7 – without the “help” of the European Parliament and theCouncil of Ministers?

For more information see:
http://europa.eu.int/
comm/environment/wssd/index_en.html

andhttp://europa.eu.int/comm/dgs/
research/organisation_en.html

Ruiz: It’s difficult to say at this stage what will be the orientations for FP7 and beyond. But
we should not apply for a large increase in budget without very solid arguments. The
European Fusion Programme must be strong. In order to achieve this, there are clearlyfinancial needs. But an effective response of the programme, in organisation and substance, to the forthcoming challenges is also essential. When preparing the fusion part ofits proposal for FP7 it can be expected that the Commission will assess the coherence
and the efficiency of the fusion programme and its relation with our possible international
partners. But as you know, the decision will belong ultimately to the budgetary Authority,
i.e. the European Parliament and the Council, and both Institutions will likely pay also
great attention to how the programme is adapting itself to the realization of ITER.
Interview: D. Lutz-Lanzinger

page 3

EFDA Fusion NewsletterITER
FZ Karlsruhe: Testing of the Toroidal Field Model Coil successfully completed
The ITER Toroidal Field Model Coil (TFMC) was built by European industry according
to the conceptual design, which was elaborated by the European Associations under thecoordination of EFDA. The objective of the project is to develop and demonstrate thesuperconducting magnet technology to a level that will allow the ITER toroidal field coils to
be built with confidence. The construction and test of the TFMC is one of the seven large
ITER R & D projects within the ITER activities.
After the first batch of tests in 2001, the TFMC was tested in the second half of 2002 in
the background field of the existing Euratom Large Coil Task (LCT) coil in the TOSKA facility at Forschungszentrum Karlsruhe (Germany). The aim of the TFMC test phases was toverify the design concept and the industrial manufacturing procedures, as well as the achievable tolerances. To validate the design parameters, the mechanical strength of the structures
and the current carrying capacity were tested at the rated values of 70 kA, 8.8 T and 4.5 K.
Furthermore the operation limits of the “Cable-in-Conduit” conductor were to be checked.
The testing of the model coil was organized in two phases. During Phase I, which was
carried out in 2001, the TFMC was tested as a single coil:• June, 25: The cool down started. The circuits of the coil were cooled by supercritical
Helium, which maintains its cooling power by forced mass flow driven by pumps operating at 4.5 K.
• July, 6: The transition to the superconducting state was reached for the first time.
• July, 23: At the end of the ITER Engineering Design Activities (EDA), the TFMC
operated as a single coil reached its maximum current of 80 kA.
The TFMC was intentionally quenched nine times, before and after being cycled, without
counting safety discharges. There were no negative consequences arising from thequenches or from the cycling.
For preparing Phase II the ITER TFMC and the Euratom LCT coil were assembled as a single structure and re-installed in the TOSKA vacuum vessel. This was completed in the firsthalf of 2002.
• August, 20: the cool down started.
• September, 3: the superconducting state in TFMC was reached again• September, 26: the coil testing of phase II started. The TFMC was energized alone
up to 80 kA, which repeated the result of last year’s test.
The Euratom LCT coil, providing the background field for thetest of TFMC, was also tested alone: first at a winding temperature of 4.5 K to a maximum current of 11.3 kA, and later at a
winding temperature of less than 3.1 K to a maximum current of
16 kA. Finally the coil assembly was energized to the rated
values of 70 kA in TFMC and 16 kA in LCT. This corresponds to8.78 T maximum field at the conductor of the TFMC and 282 MJof stored energy in both coils.
In order to check the mechanical rigidity of both winding packand coil case, the TFMC was cycled in the background field of
the Euratom LCT coil, which was kept in steady state operation
at 16 kA while the TFMC was ramped up and down to the maximum current in several steps, starting at 17.5 kA and ending at
70 kA. During this second phase the TFMC was intentionallyquenched twice.
For the case of maximum currents (80kA in the TFMC and 16
kA in the Euratom LCT coil, 9.67T magnetic field at the conductor of
TFMC) the design parameters of the conductor were confirmed.
Phase II was successfully completed in December 2002. All tests
have achieved the expected results and the operating conditions for
ITER have been confirmed with a reasonable temperature margin.

The LCT project wasundertaken in the framework of an international
collaboration of Euratom,
Japan, Switzerland andthe US under the auspices of the “International
Energy Agency” (IEA).
The Euratom LCT coil
was first tested in the
TOSKA facility in 1984.

1995: The ITER TFMC
project started
1997: Engineering design
was completed
2000: The construction of
the coil based on new
design principles andmanufacturing methods
was completed
July, 23, 2001: The TFMC
reached its maximum current of 80 kA.
Dec. 2002:
The Testing of the TFMC
in the background field of
the existing LCT coil was
successfully completed.

TOSKA vessel:
4.45 m Ø, 6.6 m high
TFMC:
2.73 m wide, 0.77 m thick,
3.8 m high, weight 34 t
Intercoil structure (ICS):
4.03 m wide, 0.70 m thick,
4.67 m high, weight 24 t
LCT coil:
3.5 m wide, 0.82 m thick,4.6 m high, weight 59 t

For more information see:
http://hbksun17.fzk.de:8080/P
KF/e_index.html

EFDA Fusion Newsletter

page 4JET
JET:
Joint European Torus

Lord Sainsbury visits the Culham Science Center (UK)
MAST:
Mega Amp Spherical
Tokamak

For more information on
JET and MAST see:
http://www.jet.efda.org/

and
http://www.fusion.org.uk/mast/

The UKAEA and JET facilities at Culham (UK) welcomeda prominent visitor on 29th
November. Lord Sainsbury ofTurville, Her Majesty’s Parliamentary Under Secretary, wasbriefed on current developments in fusion research,
including the status of planningfor the ITER and the ‘Fast
Track’ proposed by the European Expert Group led byProfessors Sir David King, theUK Government Chief Scientific
Advisor. He toured JET, MASTand the Culham Innovation
Centre, showing keen interestin all areas of work.

A significant Step in the Coordination of Tokamak Experiments at World Level

ITPA:International Tokamak
Physics Activity
You can find more information on ITPA on
http://itpa.ipp.mpg.de

IEA:
International Energy
Agency, represented on
http://www.iea.org/index.html

MIT:
Massachusetts Institute ofTechnology at Cambridge(USA). Learn more about
MIT onhttp://www.psfc.mit.edu/

MHD (Magnetohydrodynamic) instabilities:
Unstable distortions of the
shape of the plasma/magnetic field system.

A unique and successful meeting was held at MIT in Cambrige (USA) on 18/19
November 2002 to consider the coordinated implementation of high priority burning tokamak plasma research on the major world tokamaks. The leaders of these facilities (JET and
ASDEX Upgrade from Europe; JT-60U from Japan; and DIII-D, C-Mod and NSTX from theU.S.) met with representatives of the Coordinating Committee of the International Tokamak
Physics Activity (ITPA) and the Executive Committees of the International Energy Agency
Implementing Agreements (IEA-IAs) on Cooperation Among the Large Tokamak Facilities
between the EU, Japan and the US, and on the Poloidal Divertor Agreement between the
EU and the US.
The ITPA Topical Physics Groups involve about 150 scientists from the EU, Japan, theRussian Federation and the US and during their meetings in October 2002 developed outline proposals for experiments on open physics issues which should be pursued in order toenhance understanding of tokamak burning plasma science for ITER. These proposals
addressed issues related to plasma confinement, internal and edge transport barriers, divertor and scrape-off layer physics, MHD instabilities, disruptions and control, steady state operation, fast particles and diagnostic developments. The meeting at MIT discussed the implementation of those outline proposals which would benefit from coordinated joint experimentson the major world tokamaks and would lead to an improved predictive capability.
Significant advances are expected from conducting identity, and dimensionally similar,
discharges on machines with different sizes and capabilities, from identifying the data needs
for better conditioned data bases, from confirming that similar effects on different machines
have the same physics basis, from establishing, characterising and determining the limitations of key operating scenarios, and from developing and transferring operational, control
and analysis techniques.
About 40 such proposals were discussed. The tokamak leaders indicated their interestin considering for 2003 eleven proposals which were well-developed for two or moretokamaks and another sixteen if they could be developed sufficiently for the programme

page 5EFDA Fusion Newsletter

planning meetings which the major tokamaks were holding in December 2002. The
remaining proposals were considered to be on-going programmatic activities that did not yet
require joint experiments. The consolidated set of coordinated experiments on the major
tokamaks during 2003 should be finalised in the middle of January 2003. The implementation of these proposals will require personnel and some hardware exchanges and these will
be carried out under the legal framework provided by the existing IEA-IAs on tokamaks.
The meeting proved to be a very productive opportunity for enhanced communication
among the leaders of the major world tokamaks, the leaders of the ITPA, and members of
the Executive Committees of the IEA-IAs. The discussions and implementation of coordinated joint experiments will add significant value to the experiments on the individual facilities, enhance progress on tokamak burning plasma physics issues and contribute to thesuccess of future burning plasma experiments such as ITER.

Fusion in Europe
Lithium - Czech Republic can help to provide the fuel of the future
Lithium is the lightest of all metals, with a density only about half that of water. It does notoccur in the metallic form, but is found as chemical compounds in small amounts in nearly
all ingeous rock and in the waters of many mineral springs, so that there are satisfactory
deposits in the earth’s crust and oceans to meet society’s current demand for lithium.
Lithium is applied as a component of a light and firm alloy, in electronics and electrical
technology and in the glass and ceramic industry. Because it has the highest specific heatof any solid element, it has found use in heat transfer applications. Lithium will also be thefeedstock for the production of one component of fusion power station fuel – tritium. In afusion reactor neutrons will transform the lithium contained in a “blanket” surrounding theplasma into tritium and helium.
Even if the total world energy production was to be covered by fusion power stations witha lithium blanket, approximately 3800 kg/GWy, lithium demand would still be only 25 %above the current pure lithium world production (6kt/y), which represents a very small fraction of world resources. Therefore, the progressive start-up of fusion power stations would
not require significant adaptation for the lithium production and a wide scale use of lithiumfor fusion based electricity production is not expected to meet any resource limitations. One
percent of global lithium resources can be found in the area of Cinovec, Krupka and Krasno
in Czech Republic. This amount would be sufficient to supply the whole European Union.
Jachymov and Cinovec are in the region of the Czech Republic’s Ore Mountains.

Scaled Superposition of Magnetic
Configurations for Comparative Studies
on ASDEX-Upgrade (AUG), DIII-D and JET.

Name:

Lithium

Symbol: Li
Atomic number: 3
Atomic weight: 6.94
Density @ 293 K:
0.53 g/cm3
Atomic vol.:13.10 cm3/molGroup: Alkali Metals
Discovered: 1817

For more information on
the Institute of Plasma
Physics at the Academyof Sciences of the Czech
Republic please see:
http://www.ipp.cas.cz

EFDA Fusion Newsletter

page 6

Fusion in Europe
In order to further progress in the integration of
the fusion programme, inview of the forthcoming
ITER activities, theAssociation Euratom-IPP
Garching (Germany) has
recently announced theopening up of the ASDEXUpgrade experimental
programme to the EU
Associations.

TEC:
Euregional cooperation of
Euratom Associations:
IPP Jülich (Germany),
Ecole Royale Militaire
Brussels (Belgium), FOM
Institute for
Plasmaphysics Rijnhuizen(Netherlands).

For more information see:
http://www.ipp.mpg.de

ASDEX-Upgrade: Experimental Programme: stronger Role of Associations
Strong links to the EU and world wide tokamak programmes already existed on ASDEX
Upgrade (Garching, Germany), but the present initiative greatly improves both the rights
and the responsibilities of the collaborating EU Associations. The experimental programme
is now decided by the ASDEX Upgrade Programme Committee, which consists at presentof 8 members of IPP and 9 members from the collaborating Associations. The Task Force leadership is also open to the Associations. For the period 2003-2004, one of the five task forces (MHD
stability) is actually led by an associate representative, Duarte Borba from IST Lisbon. In addition,
the meetings in which the programme is discussed are now open to remote access via a
videoconferencing system. The ASDEX Upgrade
intranet has also been substantially revised togive all the necessary information on planning,
execution and analysis of the ASDEX Upgrade
experiments. This initiative also includes accessto the machine experimental data via the standardised MDSplus system also used on TCV,
RFX, JET and other devices. First experiments under this structure have already shown thebenefit of close collaboration and the first results in the field of transient transport, radio frequency heating and sawtooth tailoring have been obtained in cooperation with the Istituto
Fisica Plasma-Milano (Italy), the Association Euratom-CEA Cadarache (France) and the
Trilateral Euregio Cluster (TEC), producing a range of exciting findings. As a result, at the2002 EPS conference in Montreux, 18 out of 32 ASDEX Upgrade papers had contributors
from the Associations, with 10 having an external first author.

Visit of Delegation from Finland in Garching

Finnish participants:• Mikko Karvinen (Metso
Paper Oy)
• Raimo Rantaanen,(Outokumpu Oy)• Harri Tuomisto, (Fortum
Nuclear Services Oy)• Prof. Jorma Routti, (former DG Research, EC)• Prof. Jouko Suokas(VTT)• Dr. Mervi Sibakow(TEKES)• Juha Lindén (TEKES)• Iiro Andersson (Finnu
Fusion/PrizzTech)• Pertti Pale (FinnFusion/PrizzTech)

A delegation from Finland representing industry and contributors to Finnish Fusion
Society visited the Association Euratom-IPP, the ITER International Team and the EFDA
CSU on 2 December 2002 in Garching (Germany). Their goal was to find out how their companies and associations could contribute to the skills and technologies of fusion researchwith regard to ITER.
The Meeting started with a welcome by Prof. K. Lackner (EFDA Leader) and Prof. A.
Bradshaw (Director of IPP) to put the Finnish guests in the right mood for a day rich in information. Prof. M. Kaufmann (IPP Directorate) gave an overview of the IPP Fusion programme, presented in more detail by Dr. M. Winkler (IPP), who explained how the experiences gained with Wendelstein 7-X have been benefitting industry. The involvement ofEuropean industry in the special research areas was presented by Dr. E. Salpietro (EFDA,
Magnet Structures), Dr. P. Barabaschi (ITER design), Dr. R. Andreani (EFDA technology
programme) and Dr. W. Dänner (EFDA, Vessel/In-Vessel). The delegates toured ASDEX
Upgrade and during an open discussion showed avid interest on the perspectives towards
ITER construction.

page 7

EFDA Fusion Newsletter

Fusion & China
Main topics of study inearlier tokamaks:

Fusion Research Activities in China
A contribution from Prof. Huo Yuping, ZhengZhou University (People’s Republic of China)
China is the largest developing country with a projected population of 1.6 – 2 billion people and with an energy consumption growing from the current 1.3 Billion Tons Coal
Equivalent (TCE) to more than 4 Billion TCE by 2050.
This large demand can only be accommodated in a sustainable way which would also
allow energy generation in an environmentally-friendly way. Fusion is one of the most promising candidates to solve this important issue.
The history of fusion in China goes back to the 1950’s, when Magnetic Confinement
Fusion research was first started at the Institute of Atomic Energy in Beijing.
Confinement studies of high-temperatureplasmas were carried out in several small-size
machines. In the mid 1960’s the SouthWestern Institute of Physics (SWIP) was founded by the Ministry of Nuclear Industry. With amanpower of up to 400 persons, including
both scientists and technicians, over 20 expeHL-1
HL-1M
HL-2A
1984-1992
1994-2000
2002rimental devices were built and operated,
R=1.02m,a=0.2m
R=1.02m,a=0.26m
R=1.62m,a=0.4m
Bt =3.5T, Ip=225kA Bt =3.0T, Ip=320kA
Bt =2.8T, Ip=400kA
mainly following the tokamak concept. Among
Mo Limiter
Graphite Limiter
Divertor
them, the HL-2A, derived from the German
device ASDEX.
At the end of the 1960’s, the Chinese Academy of Science founded the Plasma Physics
Department (ASIPP) within the Institute of Physics in Beijing. A small tokamak, the CT-6
was built, followed by two air-core tokamaks, the HT-6B and the HT-6M. The ASIPP began
its superconducting tokamak programme in 1990. The first success was the HT-7 machine,
an improved version of the Russian T-7, which started operations in 1994. The next step
was the design of the HT-7U, a divertor machine to study non-circular plasmas.
Plasma laboratories opened in
the 1970’s at the University of
Science and Technology of China, at
the Dalian University of Science andTechnology and at the Tsinghua
University with the aim of training
graduate students in fusion science.
SWIP and ASIPP have almost 100
graduate students in fusion science.
In the 1980’s international relationships with other fusion institutions around the world gave theopportunity to a large number ofChinese physicists and engineers tospend some time abroad and gain
experience in different fields.
Participation in the ITER project
would now be an obvious path following from the steady, but growing,
importance that fusion has gained in
the country. After having completed
a domestic evaluation of the project,
China is now considering joining
ITER as a full member.

• Plasma confinement• Plasma edge and wallconditioning (successful
use of new techniquessuch as RF boronisation,
RF siliconisation and
RF Li + Si).
Superconducting
Tokamaks:
Main focus on reactorrelevant issues: steadystate (or quasi-steadystate) operation, noninductive plasma discharges, Heating & Current
Drive operations.
HT-7U parameters:
Plasma current = 1.1 - 1.5
MA
Toroidal field on axis =3.5 T
Major Radius = 1.95 m
a=0.45m, b=0.9m,
tdis=1000s

EFDA Fusion Newsletter

page 8

Obituary

UKAEA Culham mourns for Dr. Derek Robinson FRS
Dr. Derek C. Robinson, Director of the UKAEA Fusion
Programme and Culham Science Centre, died on Monday
2 December 2002, in Oxford. After gaining a First Class
Physics degree at the University of Manchester in 1962 heembarked upon his career in fusion research with a PhD
which involved the study of plasma turbulence in ZETA. In
1968 he spent a year at the Kurchatov Institute in Moscow,
at the height of the Cold War, in a historical Anglo-Soviet
collaboration in which a team led by Dr Nichol Peacockmade crucial measurements of the temperature in the T3† Dr. D. Robinson
Tokamak. Robinson's contribution was seminal work on the1941 - 2002
theory of instabilities of plasmas. As a result of the team's
measurements, confirming that the performance of T3 actually exceeded the Soviet
claims, the tokamak became the main line for international fusion research, as it still istoday. On returning to Culham he became the driving force behind COMPASS and ultimately the UK's pioneering spherical tokamaks, START and then MAST.
Robinson was for many years a member of the JET Scientific Council and JET
Council, he was also a member of the ITER Technical Advisory Committee. He was as
adept in fusion "politics" as in the actual science and an acknowledged international
elder statesman. The many messages of condolence from colleagues across the worldshow the esteem in which he was held.

See Obituary written by
Dr. R.S. Pease, publishedin “The Independent”, 9th
December 2002:
http://www.independent.co.uk/
story.jsp?story=359899

and also Obituary fromthe Institute of Physics:
http://www.physicsweb.org/arti
cle/news/6/12/1

Personalities
For more information
see our EFDA website:

Dr. Robert Aymar to be next Director General of CERN

http://www.efda.org

The CERN Council, where the representatives of the 20 Member States of theOrganization decide on scientific programmes and financial resources, elected Dr.
Robert Aymar to succeed Prof. L. Maiani as CERN’s Director General. Dr. Aymar,
Director of the ITER International Team, is foreseen to take office on 1 January 2004. He
will serve a five-year term and will oversee the start up of CERN’s current major project,
the Large Hadron Collider (LHC) in 2007.

and additionally
http://www.jet.efda.org
http://www.iter.org

Outstanding Technical Accomplishment Award for Dr. Gianfranco Federici
The Outstanding Technical Accomplishment Award 2002 of the Fusion Energy
Division of the American Nuclear Society (ANS) was presented to Dr. Gianfranco
Federici (ITER International Team, Garching, Germany). This award was given inrecognition of his contributions in the area of theoretical and computational research on
plasma-wall materials interactions that led to the design of the ITER divertor. The award
was presented at the 15th Topical Meeting on the Technology of Fusion Energy, held in
Washington, DC, on November 17 to 21.

More information on the
Honors and Awards
Committee on
http://fed.ans.org/fed_awards.pdf

EFDA Close Support Unit - Garching
Boltzmannstr. 2
D-85748 Garching / Munich - Germany© J. Pamela (acting EFDA Leader) 2003.

phone: +49-89-3299-4237
fax: +49-89-3299-4197
e-mail: federico.casci@efda.org
editors: Federico Casci, Doris Lanzinger
graphic design: Karen Jens

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Fusion Programme which is co-ordinated and managed by the Commission.
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