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BREST (reactor) - Wikipedia The BREST design is based on a new core design that addresses some of the issues seen in the earlier designs In contrast to the earlier solid-core concepts, which were generally designed using traditional fuel rods, BREST is based on the use of fuel encapsulated in heat-conducting nitride elements
Lead-Cooled Fast-Neutron Reactor (BREST) - Nucleus An comprehensive analysis of the innovative reactor technologies of a new generation under consideration in Russia and elsewhere shows that the concept of a fast-neutron reactor with a heavy liquid-metal coolant meets higher safety and fuel supply requirements
Russia’s Brest reactor fuel plant begins pilot operation The project uses technical solutions that have proven themselves during the operation of predecessor fast reactor power units – the BN-600 (Beloyarsk unit 3) and the BN-800 (Beloyarsk 4) Justification of structural materials and fuel for the BN-1200M is based on the operation of the BN-600
First lead-cooled fast neutron reactors installation under way The lead-cooled BREST-OD-300 fast reactor is part of Rosatom's Proryv, or Breakthrough, project to enable a closed nuclear fuel cycle The 300 MWe unit will be the main facility of the Pilot Demonstration Energy Complex at the Siberian Chemical Combine site
Physics:BREST (reactor) - HandWiki The reactor uses nitride uranium-plutonium fuel, is a breeder reactor and can burn long-term radioactive waste Lead is chosen as a coolant for being high-boiling, radiation-resistant, low-activated and at atmospheric pressure
BREST (Reaktor) – Wikipedia Ein wichtiges Ziel der Entwicklung ist neben der Schließung des Brennstoffkreislaufes auch die Transmutation von minoren Aktinoiden, ähnlich wie bei dem russischen BN-800 Reaktor
BREST-OD-300 Reactor Facility: Development Stages And Justification BREST-OD-300, an innovative inherent safety fast reactor, is being developed as a pilot and demonstration prototype for the basic commercial reactor facilities of future nuclear power with a closed nuclear fuel cycle
The Brest fast reactor - Nuclear Engineering International Despite many challenges the Brest-OD-300 lead-cooled fast reactor is now being constructed in Seversk with start-up anticipated in 2028 or 2029 The goal is a closed nuclear fuel cycle By Judith Perera The steam turbine and the stator of the generator set during delivery in August 2025
PRIS - Reactor Details This page will guide you through the Power Reactor Information System (PRIS) database, widely considered to be the most authoritative data base on nuclear power reactors
Rosatom starts installation of the BREST-OD-300 4th generation reactor Rosatom has achieved a landmark milestone in construction of a power unit with the innovative fast neutron BREST-OD-300 reactor on the site of the Pilot demonstration energy complex (PDEC) in Seversk, Tomsk Region (West Siberia)