External heating

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Plasma discharge in the ASDEX Upgrade fusion device. (Credit: © IPP, www.ipp.mpg.de)

Plasma discharge in the ASDEX Upgrade fusion device.

Joule heating

Since the magnetic cage in is created by a combination of toroidal magnetic field and current flowing through , the heating for the early stages of plasma discharge is ensured by . The low ionized gas that has to become plasma resists the induced current and heats itself. But after reaching a temperature of about 10 million , the gas is mostly ionized, the resistivity decreases quickly, and the current cannot heat the plasma any more. Ten million kelvin is not enough temperature for successful , so other types of external heating have to be used. The idea behind fusion is that after a sufficiently high temperature is reached and the fusion reaction starts, the energy of generated from fusion will provide enough energy to keep the plasma hot. The fusion will be ignited and burn without the need for external heating. But first, a temperature of about 150 million kelvin has to be reached.

Three main methods are used: , , and .

Interior of the Alcator C-Mod tokamak at the MIT Plasma Science and Fusion Center. Two Ion Cyclotron Range of Frequencies (ICRF) antennas are visible to the left of the central column. A new magnetic field-aligned ICRF antenna is visible to the right of the central column. (Source: Mike Garrett, Wikipedia.org)

Interior of the Alcator C-Mod tokamak at the MIT Plasma Science and Fusion Center. Two Ion Cyclotron Range of Frequencies (ICRF) antennas are visible to the left of the central column. A new magnetic field-aligned ICRF antenna is visible to the right of the central column.

Neutral beam injection

Neutral beam injection is based on shooting high-energy particles into the plasma, where they pass their thermal energy through multiple collisions onto plasma particles. A neutral beam injector is in fact a . that are to be used, typically or , are first ionized. Then they are accelerated by the electric field to a sufficient speed. But could not enter the , as they would be deflected by the on the plasma edge, so the ions had to pass through the neutralization chamber. As neutrals, they can fly straight into the plasma centre where their energy is most needed.

Ion cyclotron heating

Ion cyclotron heating uses radio waves at frequencies corresponding to the ion cyclotron frequency (40 to 55 MHz). When an ion absorbs such a wave, it increases its . Waves are emitted into the tokamak by large antennas.

Electron cyclotron heating

could be also directly heated by electron cyclotron resonance heating. Energy is transferred to them by electromagnetic radiation at a frequency of 170 GHz, the resonant frequency of electrons. Electrons could then pass their energy to ions through collisions.

Both these principles have a lot in common with the way in which a microwave oven heats your lunch.

Electron cyclotron heating system for ITER tokamak. (Credit © ITER Organization, www.iter.org)

Electron cyclotron heating system for ITER tokamak.

Lower hybrid current drive

Beaming energy into plasma on radio frequencies could also help to solve the problem with the pulse regime of tokamaks. The current generated on the principle could not last forever, as the transformer is a pulse device. The transformer-induced current has to be replaced by another means. This could be done by “dragging” electrons through plasma with waves of certain frequencies. The principle is called lower hybrid current drive (LHCD).

Bootstrap current

To make tokamak a more viable option for power plant, the energy inserted into it should be minimized as much as possible. Ideally, the plasma during fusion will not only generate enough heat but also maintain electrical current flowing through it. Under certain conditions, the current is generated and sustained by the plasma itself with no need for external support. This is called .