The story of nuclear fusion started in 1920 when Eddington proposed that fusion is the source of energy in the sun. From around 1950, there have been numerous devices constructed to test concepts of fusion reactors, most of these devices have used the technique of Magnetic Confinement Fusion (MCF), with a few using Inertial Confinement Fusion (ICF) and some other concepts. The most successful operational devices have been MCF machines called Tokamak, a concept which originated in the Soviet Union. Two tokamaks have operated with Deuterium-Tritium fusion reactions: the Princeton TFR tokamak from 1993 and the European JET tokamak from 1997. Since then, the mainstream approach to fusion, worldwide, has been with Tokamaks. In 2007, construction started for the international ITER tokamak, which has expectations to have the first D-T operations from 2035. After ITER will come demonstration reactors, "DEMO", capable of producing electricity.


Tokamak fusion reactors

The confinement of the hot plasma in a Tokamak is achieved with complex magnetic fields which in most recent devices are produced by superconducting coils. The confinement is achieved with two main magnetic fields, a toroidal magnetic field (Bt) and a poloidal magnetic field (Bp) plus an electric field induced by a further solenoidal magnetic field. The ions and electrons of the plasma, then follow the helical magnetic field lines and are trapped in the torus inside a vacuum vessel.

Toroidal coils generate a
 magnetic field around the torus
Poloidal coils generate magnetic fields to change plasma shape
Central solenoid coil has a current, which varies with time, to drive a circulating current in the plasma.
Magnetic fields in grey, induced electric field in black

The solenoidal magnetic field induces a current in the plasma which causes ohmic heating. Additional heating is provided by external devices such as neutral beam injectors and electromagnetic wave antennae.

The illustration below shows the principal components of a tokamak fusion reactor.

The system contains:

  • Superconducting Magnets - Toroidal; Poloidal and Solenoidal.
  • Vacuum Vessel
  • First Wall (FW) - absorbing part of the heat from neutrons
  • Blanket - breeding tritium and absorbing the rest of the heat
  • Divertor - exhausting plasma at the end of confinement period
  • Shield - absorbing remaining neutrons to project magnet coils
  • RF Antenna - providing heating for plasma
  • Cryostat - helium cooling to maintain superconductivity

The enormous flux of neutrons emitted from the Deuterium-Tritium reactions in the hot plasma, pass through the plasma facing first wall and are stopped in the blanket in which a coolant is circulated going to drive a turbine for electricity generation. The blanket also has the essential task to breed tritium fuel. Beyond, the shield must reduce as much as possible the neutron flux escaping the blanket to avoid radiation damage and activation in the magnet coils outside the vacuum vessel.

An unavoidable feature of fusion reactors using the D-T reaction, is that the inner components will rapidly become radioactive due to Neutron Activation  and suffer Radiation Damage from the enormous neutron flux emitted from the fusion reactions in the plasma. The components near the plasma, such as the Breeder Blanket and the Divertor, must be frequently replaced because of the damage, requiring remote maintenance equipment. The image below indicates the complexity of the components required for such a remote handling system

Surrounding all these components is a massive concrete "Bioshield" to contain any escaped radioactivity and toxic material, resulting from any accidents. Beyond the bioshield, is a complex of building with diverse functions.

The historical progression of tokamaks has been towards larger and larger machines with the objective of making more stable plasmas and ultimately a power station with competitive electricity output. The figure below illustrates this progression in the size of the plasma.


Remaining problem with tokamaks: disruptions

The major unsolved problem of plasma confinement in tokamaks is the phenomena of "disruptions", where the plasma is lost in catastrophic manner. This plasma loss can damage the tokamak structure in a number of ways: heating of walls causing vaporization; induced currents in vacuum vessel causing mechanical stress and runaway electrons, again, damaging the plasma facing components.

In operations, the large tokamak JET experienced frequent disruptions, 2309 over the last 10 years of operation, decreasing with time as lessons were learned. Some of the disruptions were severe and on one occasion the whole machine, reportedly, moved a few centimetres in the air.

Tokamak designs for future devices have mitigation systems for disruptions to limit the damage, consisting of rapidly injecting frozen gas into the machine to modify the plasma and slow down the plasma loss.


ITER: in construction 

The ITER project is the latest in the long series of increasingly large magnetic containment devices. Construction started in 2007 and was 77% complete by the end of May 2022. 

The objectives of ITER are:

  • Produce 500 MW of thermal fusion power
  • Demonstrate the integrated operation of technologies for a fusion power plant
  • Achieve a deuterium-tritium plasma in which the reaction is sustained through internal heating
  •  Test tritium breeding
  •  Demonstrate the safety characteristics of a fusion device

ITER will never send electricity to the grid because there is no system to make the heat from the plasma work a turbine.

The ITER tokamak will have a toroid radius of 6 meters and weigh about 25000 tonnes. The magnetic confinement is provided by a complex system of superconducting coils and there are multiple external heating devices. There will be test prototype breeder blanket modules. The ITER machine is described in detail on the project official website: Machine.

ITER must prepare the way forward towards real fusion reactor and improving plasma stability will be paramount. Advancing technology will be an important achievement but the possibilities to develop new knowledge on materials and tritium breeding will be limited.


DEMO: next step

The objective of the next phase of fusion R&D, is to construct prototype fusion power plants with the extraction of energy to generate electricity.

DEMO: fusion power to electricity

While ITER is an international collaboration project, the next stage to build an actual prototype fusion reactor will consist of separate machines in different countries. Most use the word "DEMO" in their description but have different designs. The figure below indicates the EU-DEMO design which has as a basis ITER tokamak design, scaled by 1.5 times in linear dimension, giving a tokamak with a radius of 9 meters and a reactor volume about three times that of ITER.. The discussion on this website is largely associated with the EU-DEMO design.

EU-DEMO design.

The blog: There Will Be No International DEMO Reactor That Follows ITER describes the international situation for DEMO projects.