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India has been trying to develop fast breeder reactors for decades but suffered repeated delays. [72] By December 2024 the Prototype Fast Breeder Reactor is due to be completed and commissioned. [73] [74] [75] The program is intended to use fertile thorium-232 to breed fissile uranium-233. India is also pursuing thorium thermal breeder reactor ...
EBR-I used a liquid metal alloy, NaK, for cooling. NaK is liquid at room temperature. Liquid metal cooling is also used in most fast neutron reactors including fast breeder reactors such as the Integral Fast Reactor. Many Generation IV reactors studied are liquid metal cooled: Sodium-cooled fast reactor (SFR) Lead-cooled fast reactor
The integral fast reactor (IFR), originally the advanced liquid-metal reactor (ALMR), is a design for a nuclear reactor using fast neutrons and no neutron moderator (a "fast" reactor). IFRs can breed more fuel and are distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site.
Pages in category "Liquid metal fast reactors" The following 28 pages are in this category, out of 28 total. ... Prototype Fast Breeder Reactor; S. S1G reactor; S2G ...
Schematic diagram showing the difference between the loop and pool designs of a liquid metal fast breeder reactor. The pool-type has greater thermal inertia to changes in temperature, which therefore gives more time to shut down/SCRAM during a loss of coolant accident situation. The reactor is a pool type LMFBR with
The project was intended as a prototype and demonstration for building a class of such reactors, called Liquid Metal Fast Breeder Reactors (LMFBR), in the United States. The project was first authorized in 1970. [4] After initial appropriations were provided in 1972, work continued until the U.S. Congress terminated funding on October 26, 1983 ...
It would follow a 4-year replacement schedule. The MSR program closed down in the early 1970s in favor of the liquid metal fast-breeder reactor (LMFBR), [37] after which research stagnated in the United States. [38] [39] [40] As of 2011, ARE and MSRE remained the only molten-salt reactors ever operated.
It was a pool-type liquid-metal fast breeder reactor cooled with liquid sodium and a small-scale (gross 264/net 233 MW e) prototype fast breeder reactor, located at the Marcoule nuclear site, near Orange, France. Phénix had to be stopped for refueling every two months. Between 1990 and 1996, it was run sporadically.