CFR-600

CFR-600 is a type of nuclear reactor designed for fast neutron spectrum and cooled by liquid sodium. It is a part of the Generation IV reactor initiative and is being developed by Rosatom, the Russian state nuclear energy corporation. The CFR-600 is a pool-type reactor, with the reactor core, primary pumps, and intermediate heat exchangers all located within a single pool of liquid sodium.

Design and Operation

The CFR-600 is designed to operate with a thermal power of 1500 MW and an electrical power of 600 MW. The reactor core is composed of MOX fuel, a mixture of plutonium and uranium oxides. The use of MOX fuel allows the reactor to breed more fuel than it consumes, making it a breeder reactor.

The reactor is cooled by liquid sodium, which has excellent heat transfer properties and does not slow down neutrons as much as other coolants, allowing the reactor to operate in a fast neutron spectrum. This enables the reactor to burn long-lived radioactive waste, reducing the amount of waste that needs to be stored.

Safety Features

The CFR-600 includes several safety features, such as a passive cooling system that can remove heat from the reactor core without the need for active mechanical systems. The reactor also includes a core catcher, a device designed to contain the reactor core in the event of a meltdown.

Development and Future Plans

The development of the CFR-600 is part of Russia's plan to transition to a closed nuclear fuel cycle, where all spent nuclear fuel is reprocessed and reused. The first CFR-600 reactor is currently under construction in Beloyarsk, Russia, and is expected to be operational by 2026.

See Also

• Fast-neutron reactor
• Generation IV reactor
• Nuclear power in Russia

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