newsletter
newsletter
Vol 2003 / 4
August 5, 2003

E UROPEAN F USION DEVELOPEMENT AGREEMENT

News
Issued by the EFDA
Close Support Unit
Garching

New EFDA Leader appointed
Prof. Minh-Quang Tran, head of the “Centre de Recherches en Physique desPlasmas (CRPP)” at the Ecole Polytechnique Fédérale de Lausanne (EPFL),
Switzerland, has been appointed the new EFDA leader and will take up the position on
October 1st. The decision was taken at the EFDA Steering Committee meeting which
took place in Culham (UK) on June 24, 2003.

Contents

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ITER Negotiations: P - 1 Meeting at Vienna
Interview:
Jung-Hoon Han
page 2ITER:
First Neutral Beam
Injector
page 3
Association EuratomENEA / Association
Euratom -ÖAWpage 4
Association EuratomIPP-CR / Association
Euratom-IPP-Berlin
page 5
Association EuratomIPP-Berlin /30th European PhysicalSociety Conference
page 6JET:
25 June 2003
page 7.

Interview:
Michel Huguet
page 8

http://www.efda.org

On 19th June 2003 the first Preparatory Meeting (P-1) for ITER Decision Making
was held at the IAEA (International Atomic Energy Agency) in Vienna (Austria). At thismeeting the Republic of Korea joined Canada, the European Union, Japan, thePeople’s Republic of China, the Russian Federation and the United States of America
as a Participant to ITER Negotiations. Each Participant submitted its first indications ofposition for the various matters addressed in the meeting, as a basis for discussions.
At the conclusion of P-1, all of the Participants agreed that substantial progress had
been made on the path to the implementation of ITER. The next meeting, P-2, isscheduled to take place at the IAEA in Vienna on 9th October.

30th EPS Conference on Controlled Fusion and Plasma Physics
The 30th European Physical Society (EPS) Conference on Controlled
Fusion and Plasma Physics was held, during the week of July 7 - 11, 2003,
in St. Petersburg (Russian Federation), a very special and prestigious hostfor this event since Peter the Great's "Paradise" and "Venice of the North"celebrates this year its 300th anniversary.
For more information on this topic see page 6 and http://www.ioffe.ru/EPS2003/ .

EFDA Fusion Newsletter

page 2

Interview“It was time to make a move ” - Korea joins the ITER project
EFDA Newsletter (EN): Your country officially joined ITER P1 negotiation meeting in Vienna,
Austria, on June 19 and plans to join the ITER project as a partner. How long has Korea
been working on this decision and has the last push been influenced by China and the
US recently joining?
Jung-Hoon Han (JHH): Actually we started in 1999, when the Chairman of our researchcouncil, Mr. Chae Young-Bok first visited the European Union to be informed about theEuropean fusion programme. The collaboration with the ITER partners was an essential
part of the success of the KSTAR project. The last push towards ITER was indeed
caused by China and the US. Our country is close to China and since World War II wehave had a strong relationship with the US, so I agree that our decision was strongly
influenced by the Chinese and the US move.
EN: China needs fusion urgently as a future energy source. What role does fusion play in Korea?

Dr. Jung-Hoon Han
is presently heading theInternational Cooperation
Unit at the Korea Basic
Science Institute in Daejeon, Korea.
KSTAR (Korean
Superconducting Tokamak
Reactor) is a long pulse,
superconducting tokamak
being designed to explore
advanced tokamak regimes under steady state
conditions.
Parameters:
Major Radius:
1.8 m
Minor Radius:
0.5 m
Plasma Current:
2.0 MA
Pulse Length:
20 sec < t pulse < 300 sec

JHH: Korea has not such a high energy demand as China with its large population. About
40% of our electricity is generated in nuclear power plants. To reduce CO2 in the long run
we have to find an alternative to the use of fossil fuels. Therefore we view fusion as a
future generation of electricity producing power plant, replacing or upgrading the existingatomic energy resources one day. From the current point of view it’s a very logical step.
EN: The Korea Basic Science Institute (KBSI) was established in 1988. It is leading thenational fusion R&D programme which designed and constructed the superconducting
tokamak KSTAR. What is the history of fusion in your country?
JHH: Actually we started in the 1970s with Basic Plasma and Fusion Research at University
level; in the 80s and 90s we constructed small-scale fusion research devices like theSnut-79 Tokamak at Seoul National University, KT-1 Tokamak at KAERI and the KAISTTokamak and the HANBIT Plasma Research Facility at the Korean Basic Science Institute,
KBSI, at Daejeon. This institute was established in August 1988 as the first national centre
to house various user facilities and to carry out basic science research. KBSI is leading
the national fusion R&D programme which is responsible for design and construction of
the superconducting tokamak KSTAR. The experience gained during the construction andthe operation of KSTAR as an international project and, bearing in mind that it is one of
the first tokamaks with superconducting toroidal field and poloidal field coils, could be very
valuable and represent an important contribution of South Korea to ITER.
EN: Several industrial firms like Hyundai and Poscon are already involved in the KSTAR project.
Is Korean industry well prepared to take part in the ITER project? What main contributions could they provide?
JHH: I have noticed that they have a strong will to join the ITER project. In our country,
industry has a relatively short history compared to the European Union, but a goodtradition of hard working people. I think, based on the present development level, Korean
industry could do some of the conventional parts of ITER.
EN: Since June 1996 Korea has had a Cooperation Agreement with the US at government
level in the area of Fusion Energy Research and related fields. Does your government
plan agreements of similar nature also with the EU?

For more information see:
http://www.kbsi.re.kr/2001/english
http://www.pppl.gov/kstar/

JHH: Yes, actually we are in the process of preparing such an agreement. It has been discussed since 2000 and a Cooperation Agreement between the EU and Korea in the fieldof fusion has already been drafted. I think this bilateral agreement could be signed by thisyear or by March next year at the latest.
Interview: D. Lutz-Lanzinger

page 3

EFDA Fusion Newsletter

ITER
First ITER NB Injector and the ITER NB Test Facility
The ITER Neutral Beam

A 1 MeV-neutral beam injection system planned for ITER has to operate on the basis of(NB) system consists of"negative ion technology", i.e. the acceleration and neutralisation of negative rather than
two heating and current
drive (H&CD) injectors
positive hydrogen or deuterium ions as on most present NB systems today. R&D is inand of one diagnostic
progress in Europe and in Japan on the two key items: the ion source and the accelerator.
neutral beam; space,In both cases two alternatives are being considered. Such R&D activity should be completauxiliaries and services
ed by the middle of 2005.
have been foreseen for a
In the ion source, D ions can be generated either in an arc discharge or in an RF disthird H&CD NB injector.
charge. The arc discharge is produced between tungsten filaments and the source body
The energy (1MeV deutethat acts as the anode. R&D is in progress in Naka, Japan, and in Cadarache, France,rium) and power (16.5 MW
where the so called Kamaboko III source, built in Naka, is tested on the MANTIS test bed.
per injector) specifications
The RF discharge is produced with an RF generator; R&D is in progress in Garching,of the ITER NB system
Germany. In both cases small quantities of caesium are introduced into the discharge insignificantly exceed thoseorder to enhance the production of negative ions. The R&D activity on the RF dischargeof any NB system currently
source is justified, since the presently favoured arc source does not meet all requirements,
operating.
which are: a negative ion current of 40 A at a current density of 20 mA/cm2 and a pulse
duration up to 1 hour. Further obstacles are the rather limited life time of the arc filaments,
resulting in major maintenance effort, and high costs.
The negative ions can be accelerated with two different accelerators. The multi-aperture multi-grid (MAMuG) accelerator, under development in Naka, consists of 5 gaps (fourintermediate acceleration grids). In the single
aperture, single gap accelerator (SINGAP),
Power delivered to the plasma per injector
16.5 MW
under development in Cadarache, a pre-accelBeam energy
1 MeV
eration stage (~40 keV) is followed by a single
Ion species
D1 MeV acceleration stage.
Accelerated ion current
40 A
The arc discharge source and the MAMuG
Average accelerated ion current density
200 A/m2
accelerator, already developed in Naka for theCurrent density uniformity over the extraction area
± 10 %
500 keV injectors of JT-60 U, were considered
Source filling pressure
0.3 Pathe more conservative extrapolations from
Pulse length≤ 3,600 s
existing devices, and therefore they are thebasis for the ITER NB injector reference
Summary of the design parameters for heating and current drive (H&CD)
design. Both alternatives (the RF source andNB system for ITER.
the SINGAP accelerator) offer significant
advantages. The RF source would not need filaments and therefore their replacement (routine maintenance) could be eliminated. The SINGAP accelerator could offer substantial
simplification of the accelerator and of the high voltage transmission lines and power supplies. Such design simplifications would also lead to cost saving.
There is a general appreciation within the international NB community, thatan ITER-like NB system should be built and tested before the ITER NB system
is installed at the ITER site. Such an “ITER-like NB system”, should demonstrate high voltage acceleration at ITER relevant currents, to ensure that reliable
NB operation is achieved in ITER and to minimise the time required for on-sitecommissioning. Many elements of the ITER NB system should be tested atessentially full scale and at pulse lengths commensurate with those required for
ITER (~1 hour).
A possible approach to achieve this aim would be to consider the required
equipment and all associated auxiliaries as parts of the “first ITER NB injector” tobe installed initially at an ITER NB Test Facility and later at the ITER site. A formal agreement on ITER construction and site are necessary preconditions to startprocurement. The construction of the first ITER NB injector should be shared
between the ITER Partners; the European Union, Japan and the RussianFederation are likely to be involved and discussions are underway with the ITERInternational Team to prepare for such collaborative development. In the frame of
EFDA design activities, the European laboratories are close to starting the preparation for the test facility and to optimise the ITER NB system design.

EFDA Fusion Newsletter

page 4

Associations
Lower Hybrid Wave Launcher Prototype at Frascati (Italy)
ENEA (Ente per le Nuove
Tecnologie, l’Energia el’Ambiente):
http://www.enea.it/

CEA (Commissariat àl’Energie Atomique)http://www-cad.cea.fr/

ELM (edge-localizedmode) is an instability
that occurs in short periodic bursts during Hmode in divertor tokamaks. It causes transient heat and particle
loss into the divertor
which enhance erosion.
Small ELMs are useful for
impurity / density control.
The website
http:///www.oeaw.ac.at/euratom presents an overview

of the activities of the
Association EURATOMÖAW
See also:
http://www.jet.efda.org

The Lower Hybrid (LH) wave is a plasma wave of frequency between the ion and electron cyclotron resonance frequencies. An LH launched from the plasma boundary canaccelerate electrons along the field lines and thereby drive current in the plasma. Thismethod, called Lower Hybrid Current Drive (LHCD) has the higher current drive efficiency
and is used to control the edge plasma current and access advanced plasma regimes.
The Frascati Tokamak Upgrade (FTU) is preparing a test, to start in September, whichis the first stage of experimental exploration of a new concept considered for the ITER LH
wave launcher: the Passive-Active Multijunction (PAM). The PAM is a structure in which theactive wave guides are separated by passive wave guides that allow enough space for thecooling system (see photo) and neutron shielding. Since LHCD could contribute to the production of advanced plasma scenarios on ITER,
the PAM test is crucial to check the viability of
LHCD in steady-state operation. The FTU prototype, developed within a collaboration between the
Association Euratom-ENEA and Euratom-CEA, isaimed at verifying the power handling capability of
the launcher at ITER relevant densities and magnetic field values (a unique feature of FTU), thecoupling flexibility (i.e. the operational range ofdensity in front of the structure) and at validating
numerical codes developed for modelling coupling
and propagation. Comparing the number of fasterthan average electrons produced by the PAM withthat produced by a conventional grill indicated theeffectiveness of the wave launcher. For that purpose, FTU has been equipped with two new fastelectron Bremsstrahlung cameras measuring the
X-rays generated by the fast electrons produced
by lower hybrid waves. The PAM module, which
has been successfully characterised in the laboratory during 2002, is presently being
assembled on a test bed for testing at high power and will be installed in the tokamak inJuly. Subsequently, a fully equipped prototype with the cooling system foreseen for ITER
will be tested on Tore Supra (Cadarache, France) in long pulse operation.

Association Day on Plasma Physics at Association Euratom-ÖAW
On 20th May 2003 the Association EURATOM-ÖAW organised its annual Association
Day on Plasma Physics, which was hosted this year by the Institut für Allgemeine Physik at
TU Wien. At this meeting, scientists from Vienna, Innsbruck and Graz presented their current contributions to the EU Fusion Physics Programme.
Dr. Alberto Loarte from EFDA-CSU Garching gave a lecture on strategies and aims ofthe new European Task Force on Plasma-Wall Interactions. Groups at the Institut für
Ionenphysik of Universität Innsbruck and at the Institut für Allgemeine Physik at TU Wien
are investigating plasma-wall interaction phenomena and have expressed interest to contribute to the new Task Force and the accompanying technology programme.
In his lecture entitled “JET under EFDA: a cooperative effort”, Dr. Bruno Gonçalvez fromthe EFDA-CSU Culham presented an overview of the EFDA-JET Work Programme 2003
and showed the areas of special interest for the Association EURATOM-ÖAW, which are
related to mass transport in the edge plasma, ELMs, alpha-particle simulation experiments,and fast He-beam spectroscopy.
The afternoon session was opened by a short introduction on general aspects and perspectives of the Sixth EU Framework Programme for research presented by Dr. Christian
Seiser from the Austrian Ministry for Education, Science and Culture.

page 5EFDA Fusion Newsletter

Associations
Summer Training Course on the CASTOR Tokamak
Operation of the next step fusion devices, such as ITER, will require a new generation ofphysicists, which are familiar with all aspects of experimental work on tokamaks. Their practical education can be accelerated substantially by getting them in a direct touch with experimental reality. For that purpose, small-scale experiments can be instrumental. One of thoseavailable in Europe is the small but very flexible CASTOR (Czech Academy of Sciences
TORus) tokamak routinely operating in the Institute of Plasma Physics in Prague, Czech
Republic. The tokamak is equipped with basic diagnostics, a good data acquisition system
and a reasonable software package for data processing. Daily, about 50-60 reproducible
discharges with the repetition rate comparable to 10 minutes can beeasily achieved. The permanent staff is experienced in education andtraining of Czech as well as foreign students. The Czech andHungarian Euratom Associations (IPP.CR and HAS) decided to exploit
all these benefits and jointly organize the Summer Training Course(SUMTRAIC) on the CASTOR Tokamak. The first run has been successfully performed on June 2-6, 2003, with participation of ten
Hungarian students (graduate and post-graduate) and three Hungarian
supervisors. Only those students were accepted for participation who
passed an exam on a one-semester introductory course on fusion, thisway they were already familiar with concepts and theory of fusion.
The first day of the training course was devoted to an introduction of
key elements of CASTOR (vacuum, power supplies, diagnostics etc).
Several standard shots were done with students as operators andbasic experimental data were processed. The following days, theexperimental groups have performed topical measurements (focused
this time to Langmuir probes, spectroscopy and plasma fluctuations measurements)
according to a tentative shot plan. One student of each group was selected to operate thetokamak, another one took care on the particular diagnostics and the remaining students
checked and processed data. The last day was dedicated to the discussion of results andthe preparation of presentations. The training course was completed on Friday afternoon bya joint workshop, where students presented the main experimental achievements.
The next training course is envisaged to be organized in June 2004 in a similar way.
Participation from all over Europe is welcome. A web-based fusion education course
will be available for interested students well in advance at the homepage of the
Hungarian Association.

Investigations on Chemical Erosion and Hydrocarbon Film Formation at IPP-Berlin
The plasma generator PSI run by the Berlin (Germany) division of Association EuratomIPP is a stationary high current arc discharge in an axial magnetic field. This facility allows
the production of a stationary plasma column of about 2 m in length and 8 cm in diameter.
It is used for basic as well as applied research in the field of plasma physics. A number oftechnical investigations have been conducted in close contact with the EFDA group in
Garching (Germany). The problem of chemical erosion of graphite materials being foreseen
for ITER has been studied in a joint project. In this context the chemical erosion yield of various CFC materials was studied in hydrogen and deuterium discharges. It was observedthat with moderate or low flux densities (about 1021 ions /m2 s) each hydrogen ion hitting
the target has a chance of nearly 10% of releasing a methane molecule (or some othercarbon-consisting molecule) from the surface with flux densities of 2 • 1023 ions /m2 s theerosion decreases to values of about 0.5%. This is constant with observations on tokamaks(fig. 1, see next page).

For more information on
the Institute of Plasma
Physics of Czech Rebublic (ASCR), Association
Euratom-IPP-CR, see:
http://www.cas.cz/en/UFP.html

Carbon Fiber Reinforced
Material (CFC):
Such materials were chosen
for the bottom parts of the
ITER divertor vertical target
due to their resistance to thehigh heat fluxes present inthat area. However, thisimportant advantage iscounterbalanced by otherproblems, such as erosion
and codeposition.
The experimental results described on this page mitigate
the problem of erosion. In
addition, with respect to film
formation the observations
made contain a positive message but are less convincing
because of lacking knowledge
on the ITER divertor conditions.
http://www.ipp.mpg.de/de/for/b
ereiche/diagnostik/for_ber_dia_akt.html

EFDA Fusion Newsletter

page 6

Chemical Erosion Yield (at/ion)

Associations
An upgraded version of the plasma generator (PSI-2) was used
to study the erosion and deposition behavior of hydrocarbons underconditions similar to that in some areas of the ITER divertor. The
1
hydrocarbons were generated either by chemical erosion of a
10
Dgraphite target or by injections into the plasma through a nozzle. Twoprocesses are at the basis of the two phenomena: deposition of allneutral hydrocarbons which have a high sticking probability andsimultaneous erosion of the films by atomic hydrogen. Whereas
deposition proved to be nearly independent of the surface temperaIon Beams IPP
2ture, erosion strongly increases with rising temperature.
PSI2
10
JT60U outer div
Therefore there is a critical collector temperature where erosion and
ToreS 2001
deposition
are in equilibrium
ToreS 2002
and the thickness of a layer is
TEXTORPISCES
unchanged. Beyond this temJET 2001
perature erosion prevails and3films which have been pro10
19
20
21
22
23
24
10
10
10
10
10
10
duced previously are dissolved.
2 1
The critical temperature is
Ion Flux (m s )not a universal quantity but
increases with the ratio of hydroFig. 1: Chemical erosion yield of graphite as a function ofcarbon to hydrogen fluxes.
particle flux density
The critical temperatures areinferred immediately as those where the curves cut thetemperature scale (fig. 2). This is seen to happen at
T = 360 K and 380 K wall temperatures. However, theFig.2: Growth rate of hydrocarbon films vs.
flux ratio requires further investigations. Numericalsurface temperature for the two collectors
simulations and additional experiments are under way(1) close to plasma edge
(2) at a distance of 0.4 m
to assess this issue.

30th European Physical Society Conference on Controlled Fusion

V. E. Fortov, winner of the Hannes
Alfvén Prize 2003

Puschkin, Dostojewski, Achmatowa – Russia’s most important literary figures areclosely connected with St. Petersburg, a city having an impressive history not only incultural matters, but also in the fields of science, industry and trade. About 950 participantsfrom 40 countries in this year’s EPS conference were invited to enjoy the combination ofscience and great history, staying in the hotel “Saint-Petersburg”, in the city’s heart,
directly by the river Neva. In the field of plasma physics 30 plenary speakers were invited.
The oral presentations were organized in four parallel sessions and 800 posters were presented. The traditionally awarded Hannes Alfvén Prize 2003 for outstanding contributions
to plasma physics went to V. E. Fortov for his seminal contributions in the area of non-ideal
plasmas and strongly coupled Coulomb systems and for his pioneering work in thegeneration and investigation of plasmas under extreme conditions. This conference united
for the first time the four sections of the plasma physics division of the European PhysicalSociety with the aim of improving the cooperation and synergetic effects in plasma physics.
The 31st EPS conference will be held in London (UK).
From left to right: B.V. Kuteev, C.F. Teretschenko, Yu.S. Vasiliev, F. Wagner, E.P. Velikhov

EFDA Fusion Newsletter

page 7JET
25 June 2003: a Special Day at JET
From the words that P.-H. Rebut (a former director of JET) has written to celebrate the20th anniversary of the first plasma at JET it is easy to understand that it was a day of great
excitement. At that time the machine was such a complex system that all sorts of unexpected problems had to be solved, but over the next few months the current was gradually
increased and by October had reached 1 MA.
The fact that JET is still operating and produces huge amount of valuable data is ample
evidence of the success of the large team of engineers and scientists that contributed to theproject, the construction and the operation of JET.
To mark the occasion, a small exhibition has been organised in the JET K1 Inner Foyer,
with photos and memories from some of the people present on Day 1. The Avo meter usedon Day 1 was also on show. The full message from P-H Rebut and a selection of photos ofDay 1 are available in our public
webpage, http://www.jet.efda.org.
It was a touching coincidence
that the life and work of Dr Derek
Robinson FRS, who was the
Culham Director and Head of the
EURATOM/UKAEA Association
before he died in December 2002,
was commemorated on the verysame day at the Culham ScienceCentre. Some of the senior representatives of the international
fusion community came from allover the world to take part in a
daylong seminar.
Well over two hundred colleagues, including many former
staff, heard fulsome tributes paid
to Derek’s work from leaders of
The first plasma in JET
the fusion community in Russia,
where he had spent a year in1968 as part of a Culham team confirming Soviet claims for theirfusion experiment T-3. This work led to the subsequent development of the tokamak as the main line of fusion research throughout the world.
Derek’s major input to international research during his careerof almost forty years was also recognised by speakers fromJapan, China, the USA and mainland Europe, including his role inpreparing for ITER. The Associate Leader for JET, Dr Jérôme
Paméla, chaired the International Session on future perspectives
for fusion and also presented the European contribution, recalling
Derek’s strong support for JET and his participation over many
years in the JET Scientific Council and JET Council.

Derek Robinson (right) at
Lev A Artsimovich dacha in 1968
(courtesy of Nick Peacock)"JET came to life with thefirst plasma on June 25th
1983 after five years offrantic construction. It wasa great day even if a
plasma of only a few kA
was achieved. At this time
all the elements of themachine were not yet
tested including the plasma positioning which was
not active; nevertheless
JET was in operation"
P.-H. Rebut, June 2003

EFDA Fusion Newsletter

page 8Interview
More than 30 years for fusion – Michel Huguet leaves ITER Naka
EFDA Newsletter (E.N.): You started your scientific career at the Ecole Supérieure d’Electricité in Paris(France) and you complete it as Head of the ITER Joint Work Site at Naka (Japan). The distance
between Paris and Naka is about 10 000 km. What were for you the most important milestones
along the way?
Michel Huguet (M.H.): At the Ecole Supérieure d’Electricité I was still a student. I started work at
University for my Doctorate. Basically there are three milestones in my career. The first one waswhen I left my job at University to join fusion research at the French Atomic Energy Commission(CEA) at Fontenay-aux–Roses in 1969. I was attracted by fusion as a combination of engineeringand physics. After having built the tokamak there, the second milestone was when I was asked tojoin the JET team at Culham in England where I stayed a total of 19 years and became JET
Associate Director. At the end of ‘91, I had to take the most difficult decision: I was offered theposition of ITER Deputy Director at Naka, which appeared to be rather difficult and risky for mycareer because of technical problems and organizational difficulties with ITER. But I wanted to get
involved in the design of ITER, and hopefully the construction, and trusted Dr. Rebut, who was the
ITER director at that time, and so I went to Naka.
E.N.: What feelings do you remember on June 25, 1983, when JET started operation and the operator’snote was “first light, a bit of current”?
M.H.: This first JET plasma was indeed much publicised, but for the JET team it was just one step within
the commissioning of the machine and this had started several months before. But nevertheless it
was something significant and I would say the main feeling was relief that the systems wereapparently working as expected. But I was much more satisfied a few months later, at the end of
1983, when the first plasma with a current of 1 Million Ampere was achieved. This was for me thereal confirmation that the machine was working well.
E.N.: The construction schedule for JET was 5 years, that for ITER is foreseen to be 8 years, do you
think this schedule will be kept?
M.H.: Something that helped JET with its very tight schedule was that, at the time the project was established, we already had manufacturing contracts placed for prototypes of the toroidal field coils andthe vacuum vessel. In the case of ITER, after the establishment of the project, about two years will
be needed to obtain the license to construct and then, seven years will be required for actual
construction. Finally, one more year will be used for commissioning to obtain the first plasma. So thetotal time to achieve the first plasma is about 10 years. I think for ITER it is still a very tight schedule,
but if ITER is given a strong construction team and an effective organization and project control,
I don’t see why this schedule could not be met.
E.N.: Your official work for ITER as Head of the ITER Joint Work Site at Naka ends on June 30. Have you
as a French national already been “Japanized” or are you happy to return to your home country?
M.H.: Working with the International Team, the Japanese Home Team and the other Home Teams has
been stimulating and a very positive experience. For me, the most important part of my work has
been the success we have had with the manufacture and testing of the model coils. It has been also
very enjoyable for my wife and I to discover Japanese people and culture. But now, after 30 years
abroad, I think my wife and I have earned the right to go back to France where our parents, children
and grandchildren live. Of course, I will keep in touch with my Japanese friends and colleagues…andI confess that I am taking a lot of technical documents with me to France - so this indicates that I still
feel somehow involved in fusion.
Interview: D. Lutz-Lanzinger

EFDA Close Support Unit - Garching
Boltzmannstr. 2
D-85748 Garching / Munich - Germany
phone: +49-89-3299-4237
fax: +49-89-3299-4197
e-mail: federico.casci@efda.org
editors: Federico Casci, Doris Lutz-Lanzinger
graphic design: Karen Jens

Dr. Michel Huguet (left) at
his farewell party at
EFDA/ITER Garching(Germany), together with
Dr. Robert Aymar, ITER
co-leader (right).
Find a short CV of Dr.
Huguet on our Website:
http://www.efda.org

For more information
see our EFDA website:
http://www.efda.org

and additionally
http://www.jet.efda.org
http://www.iter.org© J. Pamela (acting EFDA Leader) 2003.
This internal newsletter or parts of it may not be reproduced without permission. Text,
pictures and layout, except where noted, courtesy of the EFDA Parties.
The EFDA Parties are the European Commission and the Associates of the European
Fusion Programme which is co-ordinated and managed by the Commission.
Neither the Commission, the Associates nor anyone acting on their behalf is responsible
for any damage resulting from the use of information contained in this publication.