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In 1993, the reactor's power level was raised to 10.5 MW. In September 2002, fuel burn-up in the FBTR for the first time reached the 100,000 megawatt-days per metric ton uranium (MWd/MTU) mark. [citation needed] This is considered an important milestone in breeder reactor technology. On 7 March 2022 it attained the design power level of 40 MWt. [2]
The Fast Breeder Reactor-600 (FBR-600) or Indian Fast Breeder Reactor (IFBR) or Commercial Fast Breeder Reactor (CFBR) is a 600-MWe fast breeder nuclear reactor design presently being designed as part of India's three-stage nuclear power programme to commercialise the Prototype Fast Breeder Reactor built at Kalpakkam.
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 ...
Fast Breeder Operational 65,000 2010-07-21 Chinese Experimental Fast Reactor (65 MW, 20 MWe, sodium cooled fast-spectrum neutron reactor). Located at CIAE Beijing, construction started May 2000, first criticality July 2010. MNSR-SZ Shenzhen: Mnsr Operational 30 1988-11-01 SPR IAE Beijing: Pool Operational 3,500 1964-12-20
At first, the reactor's construction was supposed to be completed in September 2010, but there were several delays. The Prototype Fast Breeder Reactor is scheduled to be put into service in December 2024, [7] which is more than 20 years after construction began and 14 years after the original commissioning date, as of December 2023. The project ...
Mitsubishi FBR Systems, Inc. (MFBR) is a company formed on July 1, 2007, by Mitsubishi Heavy Industries to develop Fast breeder reactor technology. The establishment of the company was based on the April 2007 decision by the Japanese government to select Mitsubishi as the core company for FBR development.
U-233 was also useful for the fuel development programme for carrying out the Prototype Fast Breeder Reactor test fuel irradiation experiments in Fast Breeder Test Reactor. Apart from this, the operation aided in validating the equipment and design of system as well as the manpower training.
From April 1982 to April 1992 it operated as a national research facility to test various aspects of commercial reactor design and operation, especially relating to breeder reactors. The FFTF is not a breeder reactor itself, but rather a sodium-cooled fast neutron reactor, as the name suggests. It is stated on the site dedicated to the FFTF ...