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ITER Logo NoonYellow.svg
ITER participants.svg
Thirty-five participating nations
Formation24 October 2007
Headquarters Saint-Paul-lès-Durance, France
Bernard Bigot
ITER Exhibit (01810402) (12219071813) (cropped).jpg
Small-scale model of ITER
Type Tokamak
Construction date2013–2025
Major radius6.2 m
Plasma volume840 m3
Magnetic field 11.8 T (peak toroidal field on coil)
5.3 T (toroidal field on axis)
6 T (peak poloidal field on coil)
Heating50 MW
Fusion power500 MW
Continuous operationup to 1000 s
Location Saint-Paul-
, France

ITER (originally the International Thermonuclear Experimental Reactor [1] ) is an international nuclear fusion research and engineering megaproject, which will be the world's largest magnetic confinement plasma physics experiment. It is an experimental tokamak nuclear fusion reactor that is being built next to the Cadarache facility in Saint-Paul-lès-Durance, in Provence, southern France. [2]

Nuclear fusion process where atomic nuclei combine and release energy

In nuclear physics and nuclear chemistry, nuclear fusion is a reaction in which two or more atomic nuclei are combined to form one or more different atomic nuclei and subatomic particles. The difference in mass between the reactants and products is manifested as either the release or absorption of energy. This difference in mass arises due to the difference in atomic "binding energy" between the atomic nuclei before and after the reaction. Fusion is the process that powers active or "main sequence" stars, or other high magnitude stars.

Megaproject Extremely large-scale investment project

A megaproject is an extremely large-scale investment project.

Tokamak device using a magnetic field to confine a plasma in the shape of a torus

A tokamak is a device which uses a powerful magnetic field to confine a hot plasma in the shape of a torus. The tokamak is one of several types of magnetic confinement devices being developed to produce controlled thermonuclear fusion power. As of 2016, it is the leading candidate for a practical fusion reactor.

The ITER thermonuclear fusion reactor has been designed to produce a fusion plasma equivalent to 500 megawatts (MW) of thermal output power for around twenty minutes while 50 megawatts of thermal power are injected into the tokamak, resulting in a ten-fold gain of plasma heating power. [3] Thereby the machine aims to demonstrate the principle of producing more thermal power from the fusion process than is used to heat the plasma, something that has not yet been achieved in any fusion reactor. The total electricity consumed by the reactor and facilities will range from 110 MW up to 620 MW peak for 30-second periods during plasma operation. [4] Thermal-to-electric conversion is not included in the design because ITER will not produce sufficient power for net electrical production. The emitted heat from the fusion reaction will be vented to the atmosphere. [5] [6]

Thermonuclear fusion is a way to achieve nuclear fusion by using extremely high temperatures. There are two forms of thermonuclear fusion: uncontrolled, in which the resulting energy is released in an uncontrolled manner, as it is in thermonuclear weapons and in most stars; and controlled, where the fusion reactions take place in an environment allowing some or all of the energy released to be harnessed for constructive purposes. This article focuses on the latter.

The project is funded and run by seven member entities—the European Union, India, Japan, China, Russia, South Korea, and the United States. The EU, as host party for the ITER complex, is contributing about 45 percent of the cost, with the other six parties contributing approximately 9 percent each. [7] [8] [9] In 2016 the ITER organization signed a technical cooperation agreement with the national nuclear fusion agency of Australia, granting this country access to research results of ITER in exchange for construction of selected parts of the ITER machine. [10]

European Union Economic and political union of European states

The European Union (EU) is a political and economic union of 28 member states that are located primarily in Europe. It has an area of 4,475,757 km2 (1,728,099 sq mi) and an estimated population of about 513 million. The EU has developed an internal single market through a standardised system of laws that apply in all member states in those matters, and only those matters, where members have agreed to act as one. EU policies aim to ensure the free movement of people, goods, services and capital within the internal market, enact legislation in justice and home affairs and maintain common policies on trade, agriculture, fisheries and regional development. For travel within the Schengen Area, passport controls have been abolished. A monetary union was established in 1999 and came into full force in 2002 and is composed of 19 EU member states which use the euro currency.

India Country in South Asia

India is a country in South Asia. It is the seventh-largest country by area, the second-most populous country, and the most populous democracy in the world. Bounded by the Indian Ocean on the south, the Arabian Sea on the southwest, and the Bay of Bengal on the southeast, it shares land borders with Pakistan to the west; China, Nepal, and Bhutan to the north; and Bangladesh and Myanmar to the east. In the Indian Ocean, India is in the vicinity of Sri Lanka and the Maldives; its Andaman and Nicobar Islands share a maritime border with Thailand and Indonesia.

Japan Island country in East Asia

Japan is an island country in East Asia. Located in the Pacific Ocean, it lies off the eastern coast of the Asian continent and stretches from the Sea of Okhotsk in the north to the East China Sea and the Philippine Sea in the south.

Construction of the ITER Tokamak complex started in 2013 [11] and the building costs were over US$14 billion by June 2015. [12] The construction of the facility is expected to be completed in 2025 when commissioning of the reactor can commence. Initial plasma experiments are scheduled to begin in 2025, with full deuteriumtritium fusion experiments starting in 2035. [13] [14] If ITER becomes operational, it will become the largest magnetic confinement plasma physics experiment in use with a plasma volume of 840 cubic meters, [15] surpassing the Joint European Torus by almost a factor of 10.

Deuterium Isotope of hydrogen with 1 neutron

Deuterium is one of two stable isotopes of hydrogen. The nucleus of a deuterium atom, called a deuteron, contains one proton and one neutron, whereas the far more common protium has no neutron in the nucleus. Deuterium has a natural abundance in Earth's oceans of about one atom in 6420 of hydrogen. Thus deuterium accounts for approximately 0.02% of all the naturally occurring hydrogen in the oceans, while protium accounts for more than 99.98%. The abundance of deuterium changes slightly from one kind of natural water to another.

Tritium isotope of hydrogen with 2 neutrons

Tritium or hydrogen-3 is a rare and radioactive isotope of hydrogen, with symbol T or 3H. The nucleus of tritium contains one proton and two neutrons, whereas the nucleus of the common isotope hydrogen-1 ("protium") contains just one proton, and that of hydrogen-2 ("deuterium") contains one proton and one neutron.

Magnetic confinement fusion approach to generating fusion power that uses magnetic fields to confine fuel

Magnetic confinement fusion is an approach to generate thermonuclear fusion power that uses magnetic fields to confine the hot fusion fuel in the form of a plasma. Magnetic confinement is one of two major branches of fusion energy research, the other being inertial confinement fusion. The magnetic approach dates into the 1940s and has seen the majority of development since then. It is usually considered more promising for practical power production.

The goal of ITER is to demonstrate the scientific and technological feasibility of fusion energy for peaceful use. [16] It is the largest of more than 100 fusion reactors built since the 1950s. [16] ITER's planned successor, DEMO, is expected to be the first fusion reactor to produce electricity in an experimental environment. DEMO's anticipated success is expected to lead to full-scale electricity-producing fusion power stations and future commercial reactors. [17]

DEMO is a proposed nuclear fusion power station that is intended to build upon the ITER experimental nuclear fusion reactor. The objectives of DEMO are usually understood to lie somewhere between those of ITER and a "first of a kind" commercial station, sometimes referred to as PROTO.


ITER will produce energy by fusing deuterium and tritium to helium. Deuterium-tritium fusion.svg
ITER will produce energy by fusing deuterium and tritium to helium.

Fusion power has the potential to provide sufficient energy to satisfy mounting demand, and to do so sustainably, with a relatively small impact on the environment.

Nuclear fusion has many potential attractions. Firstly, its hydrogen isotope fuels are relatively abundant – one of the necessary isotopes, deuterium, can be extracted from seawater, while the other fuel, tritium, would be bred from a lithium blanket using neutrons produced in the fusion reaction itself. [18] Furthermore, a fusion reactor would produce virtually no CO2 or atmospheric pollutants, and its radioactive waste products would mostly be very short-lived compared to those produced by conventional nuclear reactors (fission reactors).

On 21 November 2006, the seven participants formally agreed to fund the creation of a nuclear fusion reactor. [19] The program is anticipated to last for 30 years – 10 for construction, and 20 of operation. ITER was originally expected to cost approximately €5 billion, but the rising price of raw materials and changes to the initial design have seen that amount almost triple to €13 billion. [12] The reactor is expected to take 10 years to build with completion scheduled for 2019. [20] Site preparation has begun in Cadarache, France, and procurement of large components has started. [21]

When supplied with 300 MW of electrical power, ITER is expected to produce the equivalent of 500 MW of thermal power sustained for up to 1,000 seconds. [22] This compares to JET's consumption of 700 MW of electrical power and peak thermal output of 16 MW for less than a second) by the fusion of about 0.5 g of deuterium/tritium mixture in its approximately 840 m3 reactor chamber. The heat produced in ITER will not be used to generate any electricity because after accounting for losses and the 300 MW minimum power input, the output will be equivalent to a zero (net) power reactor. [5]

Organization history

Ronald Reagan and Mikhail Gorbachev at the Geneva Summit in 1985 Reagan and Gorbachev hold discussions.jpg
Ronald Reagan and Mikhail Gorbachev at the Geneva Summit in 1985

ITER began in 1985 as a Reagan–Gorbachev [23] [24] initiative [24] [25] with the equal participation of the Soviet Union, the European Atomic Energy Community, the United States, and Japan through the 1988–1998 initial design phases. Preparations for the first Gorbachev-Reagan Summit showed that there were no tangible agreements in the works for the summit.

One energy research project, however, was being considered quietly by two physicists, Alvin Trivelpiece and Evgeny Velikhov. The project involved collaboration on the next phase of magnetic fusion research — the construction of a demonstration model. At the time, magnetic fusion research was ongoing in Japan, Europe, the Soviet Union and the US. Velikhov and Trivelpiece believed that taking the next step in fusion research would be beyond the budget of any of the key nations and that collaboration would be useful internationally.

A major bureaucratic fight erupted in the US government over the project. One argument against collaboration was that the Soviets would use it to steal US technology and know-how. A second was symbolic — the Soviet physicist Andrei Sakharov was in internal exile and the US was pushing the Soviet Union on its human rights record. The United States National Security Council convened a meeting under the direction of William Flynn Martin that resulted in a consensus that the US should go forward with the project.

Martin and Velikhov concluded the agreement that was agreed at the summit and announced in the last paragraph of this historic summit meeting, "... The two leaders emphasized the potential importance of the work aimed at utilizing controlled thermonuclear fusion for peaceful purposes and, in this connection, advocated the widest practicable development of international cooperation in obtaining this source of energy, which is essentially inexhaustible, for the benefit for all mankind." [26]

Conceptual and engineering design phases carried out under the auspices of the IAEA led to an acceptable, detailed design in 2001, underpinned by US$650 million worth of research and development by the "ITER Parties" to establish its practical feasibility.[ citation needed ] These parties, namely EU, Japan, Russian Federation (replacing the Soviet Union), and United States (which opted out of the project in 1999 and returned in 2003), were joined in negotiations by China, South Korea, and Canada (who then terminated its participation at the end of 2003). India officially became part of ITER in December 2005.

On 28 June 2005, it was officially announced that ITER would be built in the European Union in Southern France. The negotiations that led to the decision ended in a compromise between the EU and Japan, in that Japan was promised 20% of the research staff on the French location of ITER, as well as the head of the administrative body of ITER. In addition, another research facility for the project will be built in Japan, and the European Union has agreed to contribute about 50% of the costs of this institution. [27]

On 21 November 2006, an international consortium signed a formal agreement to build the reactor. [28] On 24 September 2007, the People's Republic of China became the seventh party to deposit the ITER Agreement to the IAEA. Finally, on 24 October 2007, the ITER Agreement entered into force and the ITER Organization legally came into existence.


ITER's mission is to demonstrate the feasibility of fusion power, and prove that it can work without negative impact. [29] Specifically, the project aims to:

Timeline and status

Aerial view of the ITER site in 2018 ITER site 2018 aerial view (41809720041).jpg
Aerial view of the ITER site in 2018
ITER construction status in 2018 ITER construction in 2018 (41809718461).jpg
ITER construction status in 2018

In 1978, the European Commission, Japan, United States, and USSR joined in the International Tokamak Reactor (INTOR) Workshop, under the auspices of the International Atomic Energy Agency (IAEA), to assess the readiness of magnetic fusion to move forward to the experimental power reactor (EPR) stage, to identify the additional R&D that must be undertaken, and to define the characteristics of such an EPR by means of a conceptual design. Hundreds of fusion scientists and engineers in each participating country took part in a detailed assessment of the then present status of the tokamak confinement concept vis-a-vis the requirements of an EPR, identified the required R&D by early 1980, and produced a conceptual design by mid-1981.

In 1985, at the Geneva summit meeting in 1985, Mikhail Gorbachev suggested to Ronald Reagan that the two countries jointly undertake the construction of a tokamak EPR as proposed by the INTOR Workshop. The ITER project was initiated in 1988. [30] [31]

Project milestones
1988ITER project officially initiated. [30] [31] Conceptual design activities ran from 1988 to 1990. [32]
1992Engineering design activities from 1992 [33] to 1998. [34]
2005India officially became part of ITER.
2006Approval of a cost estimate of €10 billion (US$12.8 billion) projecting the start of construction in 2008 and completion a decade later. [19]
2008Site preparation start, ITER itinerary start. [35]
2009Site preparation completion. [35]
2010 Tokamak complex excavation starts. [31]
2013Tokamak complex construction starts. [35]
2015Tokamak construction starts, [36] [37] but the schedule is extended by at least six years. [38]
2017Assembly Hall ready for equipment
2018-2025Assembly and integration: [39]
  • December 2018: Concrete support finished. [40]
  • July 2019: Half of the cryostat installed, preparing tokamak installation [41]
  • November 2020 (planned): Start welding vacuum vessel together [42]
  • June 2022 (planned): Vacuum vessel installed. [43]
  • November 2023 (planned): Installation of central solenoid starts [44]
  • Planned: Assembly ends; commissioning phase starts [39]
  • Planned: Achievement of first plasma. [45]
2035Planned: Start of deuterium–tritium operation. [46]

Reactor overview

When deuterium and tritium fuse, two nuclei come together to form a helium nucleus (an alpha particle), and a high-energy neutron.

+ 3
+ 1
+ 17.59  MeV

While nearly all stable isotopes lighter on the periodic table than iron-56 and nickel-62, which have the highest binding energy per nucleon, will fuse with some other isotope and release energy, deuterium and tritium are by far the most attractive for energy generation as they require the lowest activation energy (thus lowest temperature) to do so, while producing among the most energy per unit weight.

All proto- and mid-life stars radiate enormous amounts of energy generated by fusion processes. Mass for mass, the deuterium–tritium fusion process releases roughly three times as much energy as uranium-235 fission, and millions of times more energy than a chemical reaction such as the burning of coal. It is the goal of a fusion power station to harness this energy to produce electricity.

Activation energies for fusion reactions are generally high because the protons in each nucleus will tend to strongly repel one another, as they each have the same positive charge. A heuristic for estimating reaction rates is that nuclei must be able to get within 100 femtometers (1 × 10−13 meter) of each other, where the nuclei are increasingly likely to undergo quantum tunneling past the electrostatic barrier and the turning point where the strong nuclear force and the electrostatic force are equally balanced, allowing them to fuse. In ITER, this distance of approach is made possible by high temperatures and magnetic confinement. High temperatures give the nuclei enough energy to overcome their electrostatic repulsion (see Maxwell–Boltzmann distribution). For deuterium and tritium, the optimal reaction rates occur at temperatures on the order of 100,000,000 K. The plasma is heated to a high temperature by ohmic heating (running a current through the plasma). Additional heating is applied using neutral beam injection (which cross magnetic field lines without a net deflection and will not cause a large electromagnetic disruption) and radio frequency (RF) or microwave heating.

At such high temperatures, particles have a large kinetic energy, and hence velocity. If unconfined, the particles will rapidly escape, taking the energy with them, cooling the plasma to the point where net energy is no longer produced. A successful reactor would need to contain the particles in a small enough volume for a long enough time for much of the plasma to fuse. In ITER and many other magnetic confinement reactors, the plasma, a gas of charged particles, is confined using magnetic fields. A charged particle moving through a magnetic field experiences a force perpendicular to the direction of travel, resulting in centripetal acceleration, thereby confining it to move in a circle or helix around the lines of magnetic flux.

A solid confinement vessel is also needed, both to shield the magnets and other equipment from high temperatures and energetic photons and particles, and to maintain a near-vacuum for the plasma to populate. The containment vessel is subjected to a barrage of very energetic particles, where electrons, ions, photons, alpha particles, and neutrons constantly bombard it and degrade the structure. The material must be designed to endure this environment so that a power station would be economical. Tests of such materials will be carried out both at ITER and at IFMIF (International Fusion Materials Irradiation Facility).

Once fusion has begun, high energy neutrons will radiate from the reactive regions of the plasma, crossing magnetic field lines easily due to charge neutrality (see neutron flux). Since it is the neutrons that receive the majority of the energy, they will be ITER's primary source of energy output. Ideally, alpha particles will expend their energy in the plasma, further heating it.

Beyond the inner wall of the containment vessel one of several test blanket modules will be placed. These are designed to slow and absorb neutrons in a reliable and efficient manner, limiting damage to the rest of the structure, and breeding tritium for fuel from lithium-bearing ceramic pebbles contained within the blanket module following the following reactions:

+ 6
+ 4
+ 7
+ 4
+ 1

where the reactant neutron is supplied by the D-T fusion reaction.

Energy absorbed from the fast neutrons is extracted and passed into the primary coolant. This heat energy would then be used to power an electricity-generating turbine in a real power station; in ITER this generating system is not of scientific interest, so instead the heat will be extracted and disposed of.

Technical design

ITER Tokamak and Plant Systems (2016) (41783636452).jpg
Drawing of the ITER tokamak and integrated plant systems

Vacuum vessel

Cross-section of part of the planned ITER fusion reaction vessel. NIST Light Source Illuminates Fusion Power Diagnostics (5940503177).jpg
Cross-section of part of the planned ITER fusion reaction vessel.

The vacuum vessel is the central part of the ITER machine: a double walled steel container in which the plasma is contained by means of magnetic fields.

The ITER vacuum vessel will be twice as large and 16 times as heavy as any previously manufactured fusion vessel: each of the nine torus shaped sectors will weigh between 390 and 430 tonnes. [47] When all the shielding and port structures are included, this adds up to a total of 5,116 tonnes. Its external diameter will measure 19.4 metres (64 ft), the internal 6.5 metres (21 ft). Once assembled, the whole structure will be 11.3 metres (37 ft) high.

The primary function of the vacuum vessel is to provide a hermetically sealed plasma container. Its main components are the main vessel, the port structures and the supporting system. The main vessel is a double walled structure with poloidal and toroidal stiffening ribs between 60-millimetre-thick (2.4 in) shells to reinforce the vessel structure. These ribs also form the flow passages for the cooling water. The space between the double walls will be filled with shield structures made of stainless steel. The inner surfaces of the vessel will act as the interface with breeder modules containing the breeder blanket component. These modules will provide shielding from the high-energy neutrons produced by the fusion reactions and some will also be used for tritium breeding concepts.

The vacuum vessel has 18 upper, 17 equatorial and 9 lower ports that will be used for remote handling operations, diagnostic systems, neutral beam injections and vacuum pumping.

Breeder blanket

Owing to very limited terrestrial resources of tritium, a key component of the ITER reactor design is the breeder blanket. This component, located adjacent to the vacuum vessel, serves to produce tritium through reaction with neutrons from the plasma. There are several reactions that produce tritium within the blanket. 6
produces tritium via n,t reactions with moderated neutrons, 7
produces tritium via interactions with higher energy neutrons via n,nt reactions. Concepts for the breeder blanket include helium cooled lithium lead (HCLL) and helium cooled pebble bed (HCPB) methods. Six different Test Blanket Modules (TBM) will be tested in ITER and will share a common box geometry. Materials for use as breeder pebbles in the HCPB concept include lithium metatitanate and lithium orthosilicate. [48] Requirements of breeder materials include good tritium production and extraction, mechanical stability and low activation levels. [49]

Magnet system

The central solenoid coil will use superconducting niobium-tin to carry 46 kA and produce a field of up to 13.5 teslas. The 18 toroidal field coils will also use niobium-tin. At their maximum field strength of 11.8 teslas, they will be able to store 41 gigajoules. They have been tested at a record 80 kA. Other lower field ITER magnets (PF and CC) will use niobium-titanium for their superconducting elements. As of now the in-wall shielding blocks to protect the magnets from high energy neutrons are being manufactured and transported from the Avasarala technologies in Bangalore India to the ITER center. [50]

Additional heating

There will be three types of external heating in ITER:


The cryostat is a large 3,800-tonne stainless steel structure surrounding the vacuum vessel and the superconducting magnets, in order to provide a super-cool vacuum environment. Its thickness ranging from 50 to 250 millimetres (2.0 to 9.8 in) will allow it to withstand the atmospheric pressure on the area of a volume of 8,500 cubic meters. The total of 54 modules of the cryostat will be engineered, procured, manufactured, and installed by Larsen & Toubro Heavy Engineering in India. [52] [53]

Cooling systems

The ITER tokamak will use three interconnected cooling systems. Most of the heat will be removed by a primary water cooling loop, itself cooled by water through a heat exchanger within the tokamak building's secondary confinement. The secondary cooling loop will be cooled by a larger complex, comprising a cooling tower, a 5 km (3.1 mi) pipeline supplying water from Canal de Provence, and basins that allow cooling water to be cooled and tested for chemical contamination and tritium before being released into the Durance River. This system will need to dissipate an average power of 450 MW during the tokamak's operation. A liquid nitrogen system will provide a further 1300 kW of cooling to 80  K (−193.2 °C; −315.7 °F), and a liquid helium system will provide 75 kW of cooling to 4.5 K (−268.65 °C; −451.57 °F). The liquid helium system will be designed, manufactured, installed and commissioned by Air Liquide in France. [54] [55]


Location of Cadarache in France Cadarache (red dot) CIA World Factbook map.png
Location of Cadarache in France

The process of selecting a location for ITER was long and drawn out. The most likely sites were Cadarache in Provence-Alpes-Côte-d'Azur, France, and Rokkasho, Aomori, Japan. Additionally, Canada announced a bid for the site in Clarington in May 2001, but withdrew from the race in 2003. Spain also offered a site at Vandellòs on 17 April 2002, but the EU decided to concentrate its support solely behind the French site in late November 2003. From this point on, the choice was between France and Japan. On 3 May 2005, the EU and Japan agreed to a process which would settle their dispute by July.

At the final meeting in Moscow on 28 June 2005, the participating parties agreed to construct ITER at Cadarache in Provence-Alpes-Côte-d'Azur, France. Construction of the ITER complex began in 2007, while assembly of the tokamak itself was scheduled to begin in 2015. [21]

Fusion for Energy, the EU agency in charge of the European contribution to the project, is located in Barcelona, Spain. Fusion for Energy (F4E) is the European Union's Joint Undertaking for ITER and the Development of Fusion Energy. According to the agency's website:

F4E is responsible for providing Europe's contribution to ITER, the world's largest scientific partnership that aims to demonstrate fusion as a viable and sustainable source of energy. [...] F4E also supports fusion research and development initiatives [...] [56]

The ITER Neutral Beam Test Facility aimed at developing and optimizing the neutral beam injector prototype, is being constructed in Padova, Italy. [57] It will be the only ITER facility out of the site in Cadarache.


Thirty-five countries participate in the ITER project. ITER participants.svg
Thirty-five countries participate in the ITER project.

Currently there are seven parties participating in the ITER program: the European Union (through the legally distinct organisation Euratom), India, Japan, China, Russia, South Korea, and the United States. [21] Canada was previously a full member, but has since pulled out due to a lack of funding from the federal government. The lack of funding also resulted in Canada withdrawing from its bid for the ITER site in 2003. The host member of the ITER project, and hence the member contributing most of the costs, is the EU.

In 2007, it was announced that participants in the ITER will consider Kazakhstan's offer to join the program [58] and in March 2009, Switzerland, an associate member of Euratom since 1979, also ratified the country's accession to the European Domestic Agency Fusion for Energy as a third country member. [59] The Prime Minister of the United Kingdom announced on 20 March 2017 that the UK will be withdrawing from Euratom and future involvement in the project is unclear. The future of the Joint European Torus project, which is located in the UK, is also not certain. Some type of associate membership in Euratom is considered a likely scenario, possibly similar to Switzerland. [60] [61] In 2016, ITER announced a partnership with Australia for "technical cooperation in areas of mutual benefit and interest", but without Australia becoming a full member. [62]

ITER's work is supervised by the ITER Council, which has the authority to appoint senior staff, amend regulations, decide on budgeting issues, and allow additional states or organizations to participate in ITER. [63] The current Chairman of the ITER Council is Won Namkung, [64] and the ITER Director-General is Bernard Bigot.



As of 2016, the total price of constructing the experiment is expected to be in excess of €20 billion, [65] an increase of €4.6 billion of its 2010 estimate, [66] and of €9.6 billion from the 2009 estimate. [67] Prior to that, the proposed costs for ITER were €5 billion for the construction and €5 billion for maintenance and the research connected with it during its 35-year lifetime. At the June 2005 conference in Moscow the participating members of the ITER cooperation agreed on the following division of funding contributions: 45% by the hosting member, the European Union, and the rest split between the non-hosting members – China, India, Japan, South Korea, the Russian Federation and the USA. During the operation and deactivation phases, Euratom will contribute to 34% of the total costs. [68]

Although Japan's financial contribution as a non-hosting member is one-eleventh of the total, the EU agreed to grant it a special status so that Japan will provide for two-elevenths of the research staff at Cadarache and be awarded two-elevenths of the construction contracts, while the European Union's staff and construction components contributions will be cut from five-elevenths to four-elevenths.

It was reported in December 2010 that the European Parliament had refused to approve a plan by member states to reallocate €1.4 billion from the budget to cover a shortfall in ITER building costs in 2012–13. The closure of the 2010 budget required this financing plan to be revised, and the European Commission (EC) was forced to put forward an ITER budgetary resolution proposal in 2011. [69]

The U.S. withdrew from the ITER consortium in 2000. In 2006, Congress voted to rejoin, and again contribute financially.


Protest against ITER in France, 2009. Construction of the ITER facility began in 2007, but the project has run into many delays and budget overruns. The World Nuclear Association says that fusion "presents so far insurmountable scientific and engineering challenges". Stop-ITER Pertuis.jpg
Protest against ITER in France, 2009. Construction of the ITER facility began in 2007, but the project has run into many delays and budget overruns. The World Nuclear Association says that fusion "presents so far insurmountable scientific and engineering challenges".

A technical concern is that the 14 MeV neutrons produced by the fusion reactions will damage the materials from which the reactor is built. [71] Research is in progress to determine whether and how reactor walls can be designed to last long enough to make a commercial power station economically viable in the presence of the intense neutron bombardment. The damage is primarily caused by high energy neutrons knocking atoms out of their normal position in the crystal lattice. A related problem for a future commercial fusion power station is that the neutron bombardment will induce radioactivity in the reactor material itself. [72] Maintaining and decommissioning a commercial reactor may thus be difficult and expensive. Another problem is that superconducting magnets are damaged by neutron fluxes. A new special research facility, IFMIF, is planned to investigate this problem.

Another source of concern comes from the 2013 tokamak parameters database interpolation which says that power load on tokamak divertors will be five times the previously expected value for ITER and much more for actual electricity-generating reactors. Given that the projected power load on the ITER divertor is already very high, these new findings mean that new divertor designs should be urgently tested. [73] However, the corresponding test facility (ADX) has not received any funding as of 2018.

A number of fusion researchers working on non-tokamak systems, such as Robert Bussard and Eric Lerner, have been critical of ITER for diverting funding from what they believe could be a potentially more viable and/or cost-effective path to fusion power, such as the polywell reactor. [74] [75] Many critics accuse ITER researchers of being unwilling to face up to the technical and economic potential problems posed by tokamak fusion schemes. [74] The expected cost of ITER has risen from US$5 billion to US$20 billion, and the timeline for operation at full power was moved from the original estimate of 2016 to 2027.

A French association including about 700 anti-nuclear groups, Sortir du nucléaire (Get Out of Nuclear Energy), claimed that ITER was a hazard because scientists did not yet know how to manipulate the high-energy deuterium and tritium hydrogen isotopes used in the fusion process. [76]

Rebecca Harms, Green/EFA member of the European Parliament's Committee on Industry, Research and Energy, said: "In the next 50 years, nuclear fusion will neither tackle climate change nor guarantee the security of our energy supply." Arguing that the EU's energy research should be focused elsewhere, she said: "The Green/EFA group demands that these funds be spent instead on energy research that is relevant to the future. A major focus should now be put on renewable sources of energy." French Green party lawmaker Noël Mamère claims that more concrete efforts to fight present-day global warming will be neglected as a result of ITER: "This is not good news for the fight against the greenhouse effect because we're going to put ten billion euros towards a project that has a term of 30–50 years when we're not even sure it will be effective." [77]

ITER is not designed to produce electricity, but made as a proof of concept reactor for the later DEMO project. [78]

Responses to criticism

Proponents believe that much of the ITER criticism is misleading and inaccurate, in particular the allegations of the experiment's "inherent danger." The stated goals for a commercial fusion power station design are that the amount of radioactive waste produced should be hundreds of times less than that of a fission reactor, and that it should produce no long-lived radioactive waste, and that it is impossible for any such reactor to undergo a large-scale runaway chain reaction. [79] A direct contact of the plasma with ITER inner walls would contaminate it, causing it to cool immediately and stop the fusion process. In addition, the amount of fuel contained in a fusion reactor chamber (one half gram of deuterium/tritium fuel [21] ) is only sufficient to sustain the fusion burn pulse from minutes up to an hour at most, whereas a fission reactor usually contains several years' worth of fuel. [80] Moreover, some detritiation systems will be implemented, so that, at a fuel cycle inventory level of about 2 kg (4.4 lb), ITER will eventually need to recycle large amounts of tritium and at turnovers orders of magnitude higher than any preceding tritium facility worldwide. [81]

In the case of an accident (or sabotage), it is expected that a fusion reactor would release far less radioactive pollution than would an ordinary fission nuclear station. Furthermore, ITER's type of fusion power has little in common with nuclear weapons technology, and does not produce the fissile materials necessary for the construction of a weapon. Proponents note that large-scale fusion power would be able to produce reliable electricity on demand, and with virtually zero pollution (no gaseous CO2, SO2, or NOx by-products are produced).

According to researchers at a demonstration reactor in Japan, a fusion generator should be feasible in the 2030s and no later than the 2050s. Japan is pursuing its own research program with several operational facilities that are exploring several fusion paths. [82]

In the United States alone, electricity accounts for US$210 billion in annual sales. [83] Asia's electricity sector attracted US$93 billion in private investment between 1990 and 1999. [84] These figures take into account only current prices. Proponents of ITER contend that an investment in research now should be viewed as an attempt to earn a far greater future return.[ citation needed ] Also, worldwide investment of less than US$1 billion per year into ITER is not incompatible with concurrent research into other methods of power generation, which in 2007 totaled US$16.9 billion. [85]

Supporters of ITER emphasize that the only way to test ideas for withstanding the intense neutron flux is to experimentally subject materials to that flux, which is one of the primary missions of ITER and the IFMIF, [21] and both facilities will be vitally important to that effort. [86] The purpose of ITER is to explore the scientific and engineering questions that surround potential fusion power stations. It is nearly impossible to acquire satisfactory data for the properties of materials expected to be subject to an intense neutron flux, and burning plasmas are expected to have quite different properties from externally heated plasmas.[ citation needed ] Supporters contend that the answer to these questions requires the ITER experiment, especially in the light of the monumental potential benefits.

Furthermore, the main line of research via tokamaks has been developed to the point that it is now possible to undertake the penultimate step in magnetic confinement plasma physics research with a self-sustained reaction. In the tokamak research program, recent advances devoted to controlling the configuration of the plasma have led to the achievement of substantially improved energy and pressure confinement, which reduces the projected cost of electricity from such reactors by a factor of two to a value only about 50% more than the projected cost of electricity from advanced light-water reactors.[ citation needed ] In addition, progress in the development of advanced, low activation structural materials supports the promise of environmentally benign fusion reactors and research into alternate confinement concepts is yielding the promise of future improvements in confinement. [87] Finally, supporters contend that other potential replacements to the fossil fuels have environmental issues of their own. Solar, wind, and hydroelectric power all have a relatively low power output per square kilometer compared to ITER's successor DEMO which, at 2,000 MW, [88] would have an energy density that exceeds even large fission power stations.[ citation needed ]

Similar projects

Precursors to ITER were EAST, SST-1, KSTAR, JET, [89] and Tore Supra. [90] Similar reactors include the Wendelstein 7-X. [91] Other planned and proposed fusion reactors include DEMO, [92] NIF, [93] HiPER, [94] and MAST, [95] as well as CFETR (China Fusion Engineering Test Reactor), a 200 MW tokamak. [96] [97] [98] [99]

See also

Related Research Articles

A fusion rocket is a theoretical design for a rocket driven by fusion propulsion which could provide efficient and long-term acceleration in space without the need to carry a large fuel supply. The design relies on the development of fusion power technology beyond current capabilities, and the construction of rockets much larger and more complex than any current spacecraft. A smaller and lighter fusion reactor might be possible in the future when more sophisticated methods have been devised to control magnetic confinement and prevent plasma instabilities. Inertial fusion could provide a lighter and more compact alternative, as might a fusion engine based on an field-reversed configuration.

Fusion power type of electricity generation

Fusion power is a proposed form of power generation that would generate electricity by using heat from nuclear fusion reactions. In a fusion process, two lighter atomic nuclei combine to form a heavier nucleus, while releasing energy. Devices designed to harness this energy are known as fusion reactors.

This timeline of nuclear fusion is an incomplete chronological summary of significant events in the study and use of nuclear fusion.

Joint European Torus facility in Oxford, United Kingdom

JET, the Joint European Torus, is the world's largest operational magnetically confined plasma physics experiment, located at Culham Centre for Fusion Energy in Oxfordshire, UK. Based on a tokamak design, the fusion research facility is a joint European project with a main purpose of opening the way to future nuclear fusion grid energy.

JT-60 is a large research tokamak, the flagship of Japan's magnetic fusion program, previously run by the Japan Atomic Energy Research Institute (JAERI) and currently run by the Japan Atomic Energy Agency's (JAEA) Naka Fusion Institute in Ibaraki Prefecture. It is properly an advanced tokamak, including a D-shaped plasma cross-section and active feedback control.

Tokamak Fusion Test Reactor

The Tokamak Fusion Test Reactor (TFTR) was an experimental tokamak built at Princeton Plasma Physics Laboratory (PPPL) circa 1980 and entering service in 1982. TFTR was designed with the explicit goal of reaching scientific breakeven, the point where the heat being released from the fusion reactions in the plasma is equal or greater than the heating being supplied to the plasma by external devices to warm it up.

Aneutronic fusion is any form of fusion power in which the majority of the energy released is carried by charged particles. While the lowest-threshold nuclear fusion reactions release up to 80% of their energy in the form of (uncharged) neutrons, there also exist reactions in which the energy is released in the form of charged particles, typically protons or alpha particles. Successful aneutronic fusion would greatly reduce problems associated with neutron radiation such as ionizing damage, neutron activation and requirements for biological shielding, remote handling and safety.

Fusion energy gain factor

The fusion energy gain factor, usually expressed with the symbol Q, is the ratio of fusion power produced in a nuclear fusion reactor to the power required to maintain the plasma in steady state. The condition of Q = 1, when the power being released by the fusion reactions is equal to the required heating power, is referred to as breakeven, or in some sources, scientific breakeven.

National Spherical Torus Experiment

The National Spherical Torus Experiment (NSTX) is a magnetic fusion device based on the spherical tokamak concept. It was constructed by the Princeton Plasma Physics Laboratory (PPPL) in collaboration with the Oak Ridge National Laboratory, Columbia University, and the University of Washington at Seattle.


The KSTAR is a magnetic fusion device at the National Fusion Research Institute in Daejeon, South Korea. It is intended to study aspects of magnetic fusion energy which will be pertinent to the ITER fusion project as part of that country's contribution to the ITER effort. The project was approved in 1995 but construction was delayed by the East Asian financial crisis which weakened the South Korean economy considerably; however the construction phase of the project was completed on September 14, 2007. The first plasma was achieved in June 2008.

The beta of a plasma, symbolized by β, is the ratio of the plasma pressure to the magnetic pressure. The term is commonly used in studies of the Sun and Earth's magnetic field, and in the field of fusion power designs.

A Riggatron is a magnetic confinement fusion reactor design created by Robert W. Bussard in the late 1970s. It is a tokamak on the basis of its magnetic geometry, but some unconventional engineering choices were made. In particular, Riggatron used copper magnets positioned inside the lithium blanket, which was hoped to lead to much lower construction costs. Originally referred to as the Demountable Tokamak Fusion Core (DTFC), the name was later changed to refer to the Riggs Bank, which funded development along with Bob Guccione, publisher of the adult magazine Penthouse.

IGNITOR is the Italian name for a nuclear research project of magnetic confinement fusion, developed by ENEA Laboratories in Frascati. Construction is not complete.

SST-1 is a plasma confinement experimental device in the Institute for Plasma Research (IPR), an autonomous research institute under Department of Atomic Energy, India. It belongs to a new generation of tokamaks with the major objective being steady state operation of an advanced configuration plasma. It has been designed as a medium-sized tokamak with superconducting magnets.

Plasma-facing material

In nuclear fusion power research, the plasma-facing material (PFM) is any material used to construct the plasma-facing components (PFC), those components exposed to the plasma within which nuclear fusion occurs, and particularly the material used for the lining the first wall or divertor region of the reactor vessel.

Lockheed Martin Compact Fusion Reactor

The Lockheed Martin Compact Fusion Reactor (CFR) is a proposed nuclear fusion reactor project at Lockheed Martin’s Skunk Works. Its high-beta configuration, which implies that the ratio of plasma pressure to magnetic pressure is greater than or equal to 1, allows a compact fusion reactor (CFR) design and expedited development.

Dynomak is a spheromak fusion reactor concept developed by the University of Washington using U.S. Department of Energy funding.

The ARC fusion reactor is a theoretical design for a compact fusion reactor developed by the Massachusetts Institute of Technology (MIT) Plasma Science and Fusion Center (PSFC). The ARC design aims to achieve an engineering breakeven of three while being about half the diameter of the ITER reactor and cheaper to build.


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