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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 .
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.
TerraPower selected Kemmerer, Wyoming as the site for a 345 MWe Natrium reactor using a molten salt energy storage system. The reactor can temporarily boost output to 500 MWe, enabling the plant to integrate with renewable resources. [9] In June 2024 the site broke ground, beginning preparation for the as-yet unapproved reactor. [10]
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 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 BN-800 reactor (Russian: реактор БН–800) is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. The reactor is designed to generate 880 MW of electrical power.
Rapsodie was an experimental nuclear reactor built in Cadarache in France.. It was France's first fast reactor, and first achieved criticality in 1967. Rapsodie was a sodium-cooled fast neutron loop-type reactor with a thermal output of 40MW and no electrical generation facilities, and closed in 1983.
ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) was a proposal for a 600 MW sodium-cooled fast breeder reactor (Generation IV), proposed by the Commissariat à l'énergie atomique (CEA). It was to be built on the Marcoule Nuclear Site in France.