Fast Breeder Test Reactor
Fast Breeder Test Reactor (FBTR) is a type of nuclear reactor that produces more fissile material than it consumes. The FBTR is a significant component of the nuclear power industry, contributing to the development of sustainable and efficient energy sources.
History[edit | edit source]
The concept of the Fast Breeder Test Reactor was first proposed in the mid-20th century, as scientists sought to improve the efficiency of nuclear power generation. The first operational FBTR was commissioned in the 1980s, marking a significant milestone in the history of nuclear energy.
Design and Operation[edit | edit source]
The FBTR operates on the principle of fast neutron breeding, in which fast neutrons are used to convert non-fissile isotopes into fissile material. This process is facilitated by a nuclear fuel core surrounded by a blanket of non-fissile material.
The reactor is designed to operate at high temperatures, which improves the efficiency of the breeding process. The heat generated by the reactor is used to produce steam, which drives a turbine to generate electricity.
Advantages and Disadvantages[edit | edit source]
The primary advantage of the FBTR is its ability to produce more fissile material than it consumes, which makes it a potentially sustainable source of nuclear power. However, the operation of an FBTR involves significant technical challenges, including the management of high temperatures and the handling of radioactive materials.
Future Prospects[edit | edit source]
The FBTR technology continues to be a subject of research and development, with the aim of improving its efficiency and safety. The successful operation of existing FBTRs provides a valuable foundation for the design of future Generation IV reactors.
See Also[edit | edit source]
References[edit | edit source]
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Contributors: Prab R. Tumpati, MD