Sodium-cooled fast reactor

Abstract Starting in the 1950s, research and development (R&D) for sodium-cooled fast reactors is now about to enter the demonstration phase for the design, construction, and operation of power plants. International collaborations such as the Generation IV International Forum (GIF) among involved countries are underway. Sodium has suitable properties as a coolant material for the fast reactor. However, design measures must be provided for its chemical reactivity. Oxide and metal mainly are used for fuel materials, and nitride is also available. The cooling system is in low pressure and high temperature and includes primary and secondary sodium cooling systems as well as water-steam systems. There are loop and pool types: the former has components of the primary system connected with piping and the latter has ones contained in the reactor vessel. GIF has been developing safety design criteria for the global standardization taking into account the lessons learned from the Fukushima Daiichi nuclear power station accident. Worldwide R&D is underway to realize the closed fuel cycle as a sustainable energy supply system.

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