Самый большой в мире российский исследовательский реактор МБИР получил теплообменник от Балтийского завода

USC's enterprise spent almost two and a half years manufacturing the intermediate heat exchanger

Employees of the special energy, mechanical, and boiler shops of the Baltic Shipyard manufactured the 40-ton product on time. It is undergoing acceptance testing, after which it will be sent to the Ulyanovsk region for installation. Currently, the company's team continues to manufacture a second similar product for the fast research reactor.

Intermediate heat exchangers belong to equipment with a long manufacturing cycle. A large, meticulous work began in 2020 with the development of working design documentation. A similar heat exchanger for a fast neutron research reactor is being manufactured at the Baltic Shipyard for the first time. This is a unique, non-serial product of non-standard dimensions. The turning of parts, assembly, and welding required jeweler's precision. Thanks to the work done, the company's specialists gained invaluable practical experience in the production of experimental units and parts.
Alexander Konovalov, General Director of the Baltic Shipyard

MBIR

The largest of the operating and under construction research reactors on the planet, which will provide the Russian nuclear industry with modern and technologically advanced research infrastructure for the next 50 years. It is located in the city of Dimitrovgrad, Ulyanovsk region, at the site of the Research Institute of Atomic Reactors.

It is assumed that the new reactor will replace the existing Russian research facility BOR-60. Its capabilities will expand the study of two-component nuclear energy technologies and closing the fuel cycle, as well as help accelerate and justify the creation of safe fourth-generation nuclear power plants.

Earlier, researchers from JSC "SSC RIAR", which is part of the Rosatom State Corporation, completed the manufacture of the first experimental batch of fuel elements (fuel rods) for MBIR. The fuel rods contain uranium-plutonium MOX fuel and have successfully passed acceptance tests, which allows proceeding to the stage of fuel production for the reactor's initial loading.

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Sources
AO «OSK»

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