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A tokamak heats a hydrogen-isotope gas until it becomes plasma, then uses a carefully shaped magnetic field to keep that electrically charged plasma from rapidly striking the reactor walls. In the plasma, deuterium and tritium nuclei can fuse, releasing energy. The key distinction: fusion power produced in the plasma is not the same as net power for the whole facility or electricity delivered to a grid.

What is a tokamak?

A tokamak is an experimental fusion machine with a doughnut-shaped, or toroidal, vacuum vessel. ITER, the international experimental tokamak, describes its purpose as creating and confining a fusion plasma with strong magnetic fields. The vessel is evacuated before a small amount of fuel gas is introduced.

The gas is heated and ionized: electrons separate from atomic nuclei, leaving a mixture of charged particles called plasma. Because those particles carry electric charge, magnetic fields can guide their motion. A tokamak combines magnetic fields from external coils with electric current flowing in the plasma. The resulting field has toroidal and poloidal components, which together form a helical path around the vessel.

Magnetic confinement does not make the particles still or trap every particle perfectly. It guides their motion and reduces how quickly hot plasma moves across the field toward the vessel walls. The goal is to keep the plasma hot and dense for long enough that fusion reactions occur at a useful rate.

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How does a tokamak make fusion conditions?

Fusion requires a combination of temperature, particle density, and confinement time. Higher temperature gives nuclei more energy for collisions; adequate density makes collisions more likely; and sufficient confinement time helps keep the plasma from expanding and losing energy too quickly. A very hot plasma alone is not enough.

ITER’s engineering handbook gives a D-T fusion triple-product criterion greater than 3 × 1021 keV·s·m-3 for the temperature range of 10–20 keV. This combines plasma density, temperature, and energy-confinement time into one measure; it is a stated criterion for that reaction range, not a universal operating specification for every fusion design.

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Heating the plasma

As ITER describes its own machine, the plasma is intended to reach about 150 million °C, and its auxiliary heating systems are described in the range of 150–300 million °C. These are ITER machine and fusion-condition figures, not a single threshold that applies identically to every reactor concept. Heating systems add energy to the plasma, while the magnetic configuration helps limit energy loss to the walls.

What happens in a deuterium-tritium fusion reaction?

The deuterium-tritium (D-T) reaction joins two hydrogen isotopes: deuterium and tritium. The products are a helium nucleus, also called an alpha particle, and a neutron. ITER identifies D-T as the most achievable and efficient reaction for laboratory fusion.

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  • The alpha particle is electrically charged, so the magnetic field can confine it. As it slows down, it transfers energy to the plasma and helps keep the plasma hot.
  • The neutron has no electric charge, so the magnetic field does not confine it. ITER says it carries approximately 80 percent of the energy produced by the D-T reaction, allowing energy to leave the plasma.

In a future power plant, surrounding structures would absorb energy from the neutrons and transfer it as heat. That heat could be used to produce steam and drive a turbine-generator, much as in other thermal power stations. This conversion happens outside the plasma; the plasma’s fusion output is not itself electricity.

What does ITER’s Q=10 target mean?

ITER’s stated design target is about 500 MW of fusion power in the plasma from 50 MW of external plasma-heating power, expressed as a plasma gain ratio of Q=10. It is a target, not an achieved operating result. The ratio compares fusion power produced in the plasma with power used to heat it; it does not include all the electricity consumed by the facility or mean that ITER will deliver ten times as much electricity as it uses.

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These distinctions matter when interpreting fusion claims:

Measure What it compares or describes What it does not establish
Plasma gain (Q) Fusion power in the plasma compared with external plasma-heating power. ITER’s stated design target is about 500 MW from 50 MW (Q=10). Net energy gain for the whole facility, or electricity delivered to a grid.
Whole-facility energy balance All energy used by a facility compared with its total energy output. ITER’s plasma target alone does not establish this balance.
Grid electricity Electrical power produced and supplied to the grid after heat conversion and facility needs are accounted for. ITER is not equipped to produce electricity.

ITER’s FAQ reports a magnetic-confinement gain record of Q=0.67 for Europe’s JET tokamak in the 1990s. That is a historical figure attributed to ITER, not a statement here about the latest independently verified record.

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Why isn’t ITER a power station?

ITER is an experiment intended to test long-pulse operation and technologies at reactor scale; it is not equipped to generate electricity. Its stated fusion-power target therefore should not be read as a commercial power-station output or proof of net electricity production.

A future fusion plant would need more than a plasma that produces substantial fusion power. It would need systems to capture neutron energy as heat, convert that heat into electricity, and meet the plant’s own energy needs. It would also need an effective fuel cycle: ITER describes tritium-breeding modules as a concept to test, while tritium self-sufficiency remains a future requirement, not a demonstrated ITER capability.

What engineering challenges remain?

Managing exhaust and impurities

Not all plasma energy stays in the confined plasma. A tokamak must manage exhaust and impurities while protecting the vessel and its internal components. ITER’s divertor is designed to handle waste gas and impurities and to withstand the machine’s highest surface heat loads.

Integrating plant-scale technologies

ITER’s handbook identifies further development and integration of technologies as necessary beyond ITER for future plants. A successful plasma experiment is one important part of fusion development, but it does not by itself demonstrate a complete electricity-generating system or a self-sustaining commercial fuel cycle.

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Further reading on magnetic confinement

For a more technical introduction to tokamak field geometry and magnetic confinement, see ITER’s educational introduction to magnetic confinement.

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