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Uses an inert gas, typically carbon dioxide, for cooling, graphite moderator, historically associated with early British reactors.

Utilizes a graphite moderator and a gas (such as helium) for cooling, can reach very high temperatures, suitable for industrial heat applications.

An evolution of the GCR, uses carbon dioxide as coolant, graphite as the moderator, and operates at higher temperatures.

Uses water as a coolant and moderator, operates at high pressure to prevent boiling, most common type used in the world, primarily for electricity generation.

Operates at supercritical pressures, combines features of PWR and BWR, offers higher thermal efficiency.

Employs thorium fuel cycle, adaptable to high-temperature operations, graphite-moderated.

Boils water to create steam directly in the reactor vessel, simpler design than PWR, uses two separate circuits for coolant and turbine.

Utilizes fast neutrons, breeds more fissile material than it consumes, typically uses a plutonium-uranium mix as fuel.

Uses light water for cooling and graphite as a moderator, known for the Chernobyl disaster, high power output.

Compact, can be built in pieces and assembled onsite, designed for safety and lower cost, ideal for locations with less energy demand or for supplementing renewable sources.

Uses spherical fuel elements called 'pebbles,' high-level gas cooling, passive safety features, and graphite moderation.

Not a reactor, but a radioactive decay heat source, used for space probes and remote applications, converts heat directly to electricity without moving parts.

Employs lead or lead-bismuth eutectic as a coolant, fast neutron spectrum, offers advantages such as high boiling temperature and low operating pressure.

Uses heavy water (D2O) as coolant and moderator, can be refueled while operating, utilizes natural uranium as fuel.

Uses a molten salt mixture as both fuel and coolant, high temperature operation, inherent safety features.

Designed to use depleted uranium, a slow-moving fission wave to breed and consume fuel, intended for long operation without refueling.

Relies on an external neutron source, cannot sustain chain reaction on its own, aimed at reducing nuclear waste through transmutation.

Utilizes liquid metal, such as sodium, for cooling, fast neutron spectrum, excellent breeding ratio.

A type of LMFBR, designed for efficient fuel use and minimal waste, integrates fuel reprocessing on-site, uses a sodium coolant.