19th IAEA Fusion Energy Conference
Lyon, France, 14-19 October 2002
Artsimovich Memorial Lecture
René PELLATHigh Commissioner for the French Atomic Energy

1. Introduction
After half a century of work, mastering on earth thermonuclear fusion to produce energy isbecoming a realistic challenge : despite its scientific and technological complexity,
considerable progress has been obtained without encountering insurmountable roadblocks.
Such progress is due for a great part to all the pioneers, as Academician Lev Andreevich
Artsimovich, who, with their talents and a visionary mind, internationally promoted the civil
use of thermonuclear fusion, a source which could help to face the long term energy demand.
To honour their faith and their investment in this challenge which would solve humankind
energy needs on a millenary scale, I will try in this Artsimovich Memorial Lecture to : situate
the fusion contribution in the future energy mix contemplated today ; survey the state of theart of fusion physics and technology fields, giving some examples ; underline the next
priority, to study a burning plasma, launching the construction of the International
Thermonuclear Experimental Reactor (ITER) as soon as possible.

2. Energy consumption, resources and needs
Mankind is confronted with a continually rising energy demand, because both the world
population and the average world power consumption per capita rise. Our energy future
depends on a number of uncertainties of technological, environmental and political nature.
Our present primary energy consumption is of the order of 9 Gtoe, most of which is producedby burning fossil fuels (≈ 87 %). However, proved fossil fuels reserves will not last for very
long. Oil and natural gas are expected to last several decades at the current rate ofconsumption, and coal a few hundred years. Moreover, the massive use of fossil fuels has
serious consequences for our environment, since large quantities of CO2 (> 1010 ton/year) are
inevitably released into the atmosphere and, indeed, measurements show a very sharp increaseof the CO2 atmosphere content during the last few decades. Higher CO2 concentrations in theatmosphere will lead to increased absorption of the infrared radiation re-emitted by the earth.
There is general agreement among specialists that this will cause the earth averagetemperature to rise, but the consequences to the climate of this increase is a hotly debatedissue. Moreover, it must not be forgotten that CO2 removal from the atmosphere is a slow
process : it takes over 100 years through slow carbon exchange between surface water anddeep ocean.
Consequently, limited fossil resources and negative side effects for the environment may
force us to introduce other energy sources as soon as possible. However, the number ofconceivable non-fossil candidates which in the long term could substantially contribute toenergy production is limited : renewables, nuclear fission and nuclear fusion.
Renewable sources (solar, wind, bio-products) are large and inexhaustible, but they sufferfrom low energy density and/or fluctuations in time. As an example, solar energy, using
photovoltaic panels with an efficiency of 10 %, requires a surface of approximately 100 km2

in western Europe to produce 1 GWe (the typical output of one single modern electric power
plant). Renewables cannot therefore be an alternative solution for our future energy needs ;they can only be a complement to other energy sources.
Fission is a well developed energy source : 17 % of the present world electric energy isproduced by nuclear reactors. To be a long term source it will need to switch from the present
generation of water reactors to breeder reactors (Fig. 1). However, it presently suffers from a
low level of acceptance by the general public, mainly because it produces highly radioactive,long-lived waste (but only a rather low volume) for which a definitive solution has not yet
been clearly indicated. Calculations of the energy needs for the XXIst century are another
hotly debated issue, since they strongly depend on the hypothesis on the rate of increase of theworld population and their per capita consumption. However, all scenarii show that a strong
increase of nuclear energy will be necessary before the middle of the century.

40000

35000

MtU : Total of millions ofNuclear energy (TW eh/y)tons of uranium extracted
FUSION

30000

23 MtU

25000

20000

7 MtU

15000

FISSION4,9 MtU

10000

5000

1,6 MtU
02000

2010

2020

2030

Fast Breeder Reactor
2040

2050

2060

2070

2080

2090

2100

2110

CalendarFigure 1 : Fission and fusion energy contribution to future world needs, for a given amountof uranium extracted. Fast Breeder Reactors would be used to maintain theannual fission energy produced (courtesy A. Simon).

Fusion is the least developed of the three non-fossil alternative energy sources, but has
particularly valuable environmental and safety advantages : inherent and passive safety ;primary fuels not radioactive and not polluting ; radiotoxicity quickly becoming lower eventhan that of coal plants ; disposal of virtually inexhaustible deuterium and lithium resources.
Calculations of the direct costs of fusion generated electricity indicate that, given only modest
optimisation of fusion physics and use of anticipated near-term structural materials, it would
be competitive. Moreover, fusion external costs are low. It is thought that fusion could
contribute to the electricity supply by the end of the century, mainly constrained by theassumed rate at which it could be deployed (Fig. 1).
The development of nuclear fusion as an energy source is of course a complex scientific andtechnical task, and it will probably need at least another half century. Two approaches to theproblem co-exist : magnetic fusion and inertial fusion.

3. Magnetic confinement
Magnetic fusion uses magnetic fields to confine the reacting particles. The more advanced
configuration is the tokamak, but other alternative configurations are still investigated,
especially stellarators. Tremendous progress has been obtained over the last thirty years,
which have seen three tokamak generations, each one with a doubling of the characteristic
dimensions : the fusion triple product (ion temperature times density times confinement time)
has increased by a factor of approximately 104, and up to 16 MW of fusion power have beenobtained in deuterium-tritium experiments in JET and TFTR. This corresponds to a Q value(ratio of fusion power to heating power) of 0.7, very near breakeven (Q=1). Although thetheoretical understanding of transport is not yet complete, consistent confinement scaling has
been found on many tokamaks, implying a common underlying transport physics. This has
allowed empirical scaling laws for the confinement to be deduced, on which extrapolations tothe next tokamak generation can be confidently based. On the experimental side, operational
control of confinement and instabilities (large scale magneto-hydrodynamical andmicroscopic) , has been demonstrated : H-mode ; better confinement and decreased Edge
Localised Modes by increasing the plasma triangularity ; internal barriers ; active feedback ofneoclassical tearing modes with electron cyclotron heating ; control of the ideal kink mode bywall stabilisation ; increase of the beta limits with low aspect ratio (Fig. 2) ; plasma purity
controlled by axi-symmetric divertors ; …

Figure 2 :  T versus normalised plasma current for conventional and spherical tokamaks(courtesy A. Sykes).

The tokamak operation is intrinsically pulsed, since it relies on the plasma current (generallyinductive) to realise the magnetic configuration, but efforts are being made towards long pulse
operation and steady-state. This introduces new challenges, both in the physics andtechnology : superconducting magnets ; effective current drive, including bootstrap ; fuellingand pumping of the discharge ; injection and exhaust of the heating and current drive powers ;active control of the profiles. One of the most challenging aspects is the heat exhaust (Fig. 3) :actively cooled plasma facing components must completely cover the interior of the vacuum
vessel, and this is a challenging industrial issue, as shown by the record of 740 MJ recently
injected and exhausted on Tore Supra. Great hope is put on the “advanced tokamak” mode ofoperation, with a large bootstrap current fraction and active profile control.

Figure 3 : Comparison of the performances of many tokamaks in terms of duration versus
convected and radiated power (courtesy B. Saoutic).

Among the alternative magnetic confinement configurations, the stellarator is the mostactively pursued. Since its magnetic configuration is realised only by external coils, it is
intrinsically steady-state, and does not have current-driven instabilities. Although stellaratorslag one generation behind tokamaks, their performances are comparable to those of tokamaksof similar size (Fig. 4), and have the advantage of high density operation and of showing
quiescent behaviour at the operational limits. Stellarators based on the “quasi-symmetry”
optimisation concept overcome the inherent stellarator disadvantages : high neo-classicallosses and low beta. However, the design of their magnetic coils is technically much moredifficult than in tokamaks.

Figure 4 : Comparison of theoretical E ISS95 and experimental E exp confinement times oftokamaks and stellarators (courtesy F. Wagner).

4. Inertial Confinement Fusion
Inertial confinement fusion (ICF) is based on the implosion of cryogenic DT capsules: adriver provides the energy necessary to concentrate the fuel so that it can sustain thepropagation of a combustion wave ; a hot spot at a very high temperature, of the order of 60
keV, is necessary to ignite this wave.
Until now lasers are the drivers most studied through two scenarii : direct drive, where thecapsule is directly irradiated by the laser, and indirect drive, where the laser light is first
converted into X-rays confined in a « hohlraum ». Indirect drive seems to be more complex
but has very useful features, such as ablation efficiency and irradiation uniformity. The newinvestigation area of the last decade is « Fast Ignition » : unlike the standard central hot spotapproach, the hot spot is made at an edge of the compression region by very short durationand powerful petawatt beams ; this third scenario has been recently very challenging for many
research teams in the world. On a lower scale, some work is also done on Pulsed Power andHeavy Ions drivers ; their use is close to the indirect drive laser scenario.
Let us see what has been mastered in laser ICF. The first neutrons from a laser shot wereobserved in 1968; several laboratories in France, Japan, Russia and US subsequently worked
on ICF. Some of their important results can be underlined : high ablation compression,densities reaching values of 100 to 600 times the DT liquid density ; plasma instabilities
control techniques using laser third harmonic and beam smoothing ; symmetry and stability
implosion improvements ; technology progress such as cryogenic targets realisation anddevelopment of megajoule lasers.
Two main issues are to be solved to ignite the DT and to obtain energy gains closed to 10 : tocontrol laser-plasma instabilities at a megajoule scale, avoiding energy backscattering ; tomaster implosion hydrodynamical instabilities which could destroy the imploding capsule orquench the hot spot.

Today, the major ICF investments are made by the US and France, which are respectively
building the National Ignition Facility (NIF) at Livermore and the Laser Megajoule (LMJ) at
Bordeaux, to achieve ignition at the beginning of the next decade (Fig. 5).

Figure 5 : View of the sites of the NIF and of the Ligne d’Intégration Laser (LIL) which is a
prototype of the LMJ.

5. The road to the Reactor : ITER
From the last half century work, a well established fusion energy basis allows today to enlarge
the research field to burning plasma studies in order to progress on the reactor road, going
through its physics, technology and socio-economics interlinked steps.
After more than 15 years of international co-operation, the ITER project is now considered by
the great majority of the scientific community as the most appropriate to produce athermonuclear plasma where heating is mainly due to  particles from DT fusion reactions
and to control it on a long duration. Its major objective is “to demonstrate the scientific andtechnological feasibility of fusion energy”. Two confinement modes are being contemplated :· The inductive ELMy H-mode with an energy amplification Q of 10 (70% of the plasma
heating coming from the  energy deposition) during a time of the order of 400s.

· The so called “advanced tokamak” mode, to generate a steady-state discharge using noninductive current drive, a Q value of 5 being expected.

Preliminary tests of the components of a future reactor are also foreseen, such as tritium
breeding blanket modules submitted to neutron flux and neutron fluence respectively of theorder of 0.5 MW.m-2 and 0.3 MW am-2. The main issues to reach such results appear to be :control of the current and the plasma pressure profiles in a  dominated discharge ; divertor
lifetime with large ELMs for the inductive mode ; tritium retention in the divertor.
Nevertheless, using the existing facilities and in particular JET (the device closest to the ITER
operational domain; Fig. 6), a better knowledge of the planned ITER operation isprogressively acquired, increasing the confidence in the projected performances.

Figure 6 : JET and expected ITER operating density-confinement space(courtesy K. Lackner).

ITER, the first priority on the reactor road, requires a 4.6 billions of euros investment and its
construction will need 10 years, followed by operation and decommissioning periods
respectively of 20 years and 15 years. Started in November 2001, ITER negotiations between
Canada, European Union (EU), Japan and Russian Federation, are progressing, with thepossible future US and China participation. They deal with status, site and financial
participations tightly linked, licensing, management, … and could be achieved mid-2003 if asite would be chosen in time among the four offers : Clarington in Canada ; Cadarache inFrance and Vandellos in Spain as EU offers ; Rokkasho in Japan. If concluded mid-2003,
these negotiations would allow a construction start around 2005.
What could be the strategy towards the reactor, with the goal of a commercial reactor for theend of this century ?
First, to reach the ITER objectifs and on the long term to select the optimised reactor
configuration, it is necessary to develop an appropriate “accompanying programme”. In
particular, superconducting facilities, tokamaks and stellarators, could efficiently contribute tothe study of steady-state discharges, such as the following facilities in construction, HT-U inChina, KSTAR in Korea and W7-X in EU.

Second, technology and economics reactor issues have also to be progressively solved, havingin mind that this next step, ITER, would be followed by other steps, as in the EU strategy: net
electricity production with DEMO and economically competitive electricity generation withPROTO. In particular, the development of low activation and radiation resistant structural
materials and of tritium breeding blankets has to be properly phased in time with these steps ;the required material neutron irradiations could be done with neutron sources (as theInternational Fusion Materials Irradiation Facility project) and on these future facilities.
At last, at a pace depending on the scientific and technological results and on the investmentsallowed for fusion energy, it could be foreseen to progress somewhat faster along the reactor
road, the recently introduced Fast Track concept envisioning a commercial reactor for the2050 horizon.

6. Conclusion
The past 50 years fusion work has established a well founded physics and technology basis :high fusion performances have been realized, reaching 16 MW of peak power and 20 MJ ofenergy with the Joint European Torus (JET).
Today, the demonstration of a sustained burning plasma is the next goal which will open theroute towards the reactor. To reach this goal, we have to launch the construction of theInternational Thermonuclear Experimental Reactor (ITER) as soon as possible, choosing asite and concluding its negotiations.
At last, we must strengthen the international broad-based collaboration in order to harness thebenefits of fusion for mankind.

Acknowledgements
I would like to acknowledge the fruitful exchanges I had with our fusion Community on
progress done and on the burning plasma challenge. I thank all of those who helped me toprepare this Artsimovich Memorial Lecture, in particular Claudio de Michelis and the CEA
Département de Recherche sur la Fusion Contrôlée, Pascal Lallia, Serge Païdassi, Alain
Simon, Alan Sykes, Jacques Tassart, Friedrich Wagner and Jean-Paul Watteau who coordinated the preparation of this lecture.

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