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On 31 July 2024, the Atomic Energy Regulatory Board (AERB) approved adding nuclear fuel and starting the chain reaction. [21] It is expected to be operational by end of 2025. [22] A few lower power physics experiments will be carried out once sustained nuclear chain reaction is achieved.
The BREST reactor is a Russian conceptual design for a lead-cooled fast reactor based on a generation IV reactor.Two designs are planned, the BREST-300 (300 MWe) and the BREST-1200 (1200 MWe).
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.
The reactor was designed to produce 40 MW of thermal power and 13.2 MW of electrical power. The initial nuclear fuel core used in the FBTR consisted of approximately 50 kg (110 lb) of weapons-grade plutonium. The FBTR has rarely operated at its designed capacity and had to be shut down between 1987 and 1989 due to technical problems.
International Fast For Life (IFFL) was a prolonged fast in favor of nuclear disarmament that spawned the Fast For Life movement. The context of this event took place during an era of escalation of the U.S./Russian Cold War. Its purpose was to promote a redirection of international government efforts away from nuclear arms and toward feeding the ...
Gas-cooled fast reactor scheme. The gas-cooled fast reactor (GFR) system is a nuclear reactor design which is currently in development.Classed as a Generation IV reactor, it features a fast-neutron spectrum and closed fuel cycle for efficient conversion of fertile uranium and management of actinides.
The China Experimental Fast Reactor (CEFR) is China's first fast nuclear reactor, and is located outside Beijing at the China Institute of Atomic Energy.It aims to provide China with fast-reactor design, construction, and operational experience, and will be a key facility for testing and researching components and materials to be used in subsequent fast reactors.
In a fission nuclear reactor, uranium-238 can be used to generate plutonium-239, which itself can be used in a nuclear weapon or as a nuclear-reactor fuel supply. In a typical nuclear reactor, up to one-third of the generated power comes from the fission of 239 Pu, which is not supplied as a fuel to the reactor, but rather, produced from 238 U. [5] A certain amount of production of 239