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A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium. The initials SFR in particular refer to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), and one based on the metal-fueled integral fast reactor .
Natrium uses liquid sodium as a coolant (reducing the cost using an ambient pressure primary loop). It then transfers that heat to molten salt, which can be stored in tanks and used to generate steam on demand, enabling the reactor to run continuously at constant power, while allowing dispatchable electricity generation. [6]
The Sodium Reactor Experiment, designed by Atomics International, was one of the chosen reactors. [6] Design of the Sodium Reactor Experiment began in June 1954, and construction was underway in April 1955. A local utility company, Southern California Edison, installed and operated a 6.5 MW electric-power generating system.
The reactor is a sodium-cooled fast reactor, which uses liquid sodium as the coolant. [4] It uses two separate sodium loops, and these are connected to a main water-cooled loop which feeds the steam generators and turbines for producing electricity. [7] The sodium coolant is pressurized to 5.5 MPa, and is heated to over 500 °C in the reactor. [6]
The sodium-cooled graphite-moderated reactor (SGR) design (of which HNFP was a demonstration) targeted economical commercial nuclear electricity. The liquid metal coolant enabled operation at temperatures sufficiently high to produce steam conditions identical to those used in fossil-fueled power plants, enhancing power conversion efficiency ...
In May 2005 the core support basket was drilled to drain the remaining sodium coolant, which effectively made the reactor unusable. However, a technical study is being pursued with regard to repairing the reactor. [citation needed] As the coolant was drained, the system was filled with high purity argon gas to prevent corrosion. The support ...
The BN-1200 reactor is a sodium-cooled fast breeder reactor project, under development by OKBM Afrikantov in Zarechny, Russia. The BN-1200 is based on the earlier BN-600 and especially BN-800, with which it shares a number of features. The reactor's name comes from its electrical output, nominally 1220 MWe.
The flammability of sodium is a risk to operators. Sodium burns easily in air and will ignite spontaneously on contact with water. The use of an intermediate coolant loop between the reactor and the turbines minimizes the risk of a sodium fire in the reactor core. Under neutron bombardment, sodium-24 is produced.