Версия от 20:51, 6 марта 2024; EducationBot(обсуждение | вклад)(Новая страница: «{{Английская Википедия/Панель перехода}} {{Short description|Breeder reactor in Tamil Nadu, India}} {{Use dmy dates|date=July 2019}} {{More citations needed|date=March 2017}} thumb|Fast Breeder Test Reactor in Kalpakkam {{coord|12.5623504|80.1645415|display=title|format=dms}} The '''Fast Breeder Test Reactor''' ('''FBTR''') is a breeder reactor located at Kalpakkam, Tamil...»)
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It first reached criticality in Шаблон:Start date and age,[2] making India the seventh nation to have the technology to build and operate a breeder reactor after United States, UK, France, Japan, Germany, and Russia. 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 Шаблон:Convert 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. From 1989 to 1992, the reactor operated at 1 MW.
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.Шаблон:Cn This is considered an important milestone in breeder reactor technology. On March 7, 2022 it attained the design power level of 40 MWt.[2]
The reactor uses a plutonium-uranium mixed carbide fuel and liquid sodium as a coolant. The fuel is an indigenous mix of 70 percent plutonium carbide and 30 percent uranium carbide. Plutonium for the fuel is extracted from irradiated fuel in the Madras power reactors and reprocessed in Tarapur.
Some of the uranium is created from the transmutation of thorium bundles that are also placed in the core.[3]
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