BREST (reactor)

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The BREST reactor ( Russian БРЕСТ, spelled out in Russian Быстрый Реактор ЕСТественной безопасности for fast reactor with inherent safety ) is a Russian reactor concept for a lead-cooled fast breeder reactor that should meet the standard of a generation IV lead-cooled reactor . There are two variants of different outputs (300 MWe and 1200 MWe) under construction or planning. The BREST reactor offers some passive safety features and should enable a closed fuel cycle.

Nitridic nuclear fuel, which has a high density (14.3 g / cm 3 ) and high thermal conductivity (20  W / ( m · K )), is used in the reactor . Lead as a coolant enables cooling through natural convection and has a very high boiling point. Furthermore, due to its high density, lead provides good shielding and enables good neutron economy.

In addition to closing the fuel cycle , an important goal of the development is also the transmutation of minor actinides , similar to the Russian BN-800 reactor.

BREST-300

A first copy will be built in Seversk from 2017 . The start of construction and construction progress suffered from several delays; In 2018, the year 2026 was named as the start of operations. The system also serves as a prototype for the BREST-1200 variant. The BREST-300 has a thermal output of 700 MW and a net electrical output of 300 MW. The coolant temperature is approx. 505 ° C when entering and 340 ° C when leaving the heat exchanger . The fuel change interval is approx. 5 years with a fuel inventory of 20.6 tons.

BREST-1200

The BREST-1200 is planned for an electrical output of 1,200 MW and a thermal output of 2,800 MW. The fuel change interval is 5 to 6 years. A construction decision should be made after initial operational experience with BREST-300, i.e. around 2030.

Individual evidence

  1. ↑ a b Yu.G. Dragunov, VV Lemekhov, AV Moiseev: Lead-Cooled Fast-Neutron Reactor (BREST). Retrieved March 19, 2017 .
  2. ↑ https://www.neimagazine.com/news/newsrussias-brest-reactor-now-scheduled-for-2026-6803677
  3. ^ AI Filin, VV Orlov, VN Leonov: DESIGN FEATURES OF BREST REACTORS. EXPERIMENTAL WORK TO ADVANCE THE CONCEPT OF BREST REACTORS. RESULTS AND PLANS . S. 75-90 .