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BREST-OD

An example of an innovative lead-cooled fast reactor of natural safety is the pilot 300 MWe reactor BREST-OD-300, which is being developed in Russia (ISTC 2001 Adamov et al. 1997). [Pg.2715]

BREST-OD-300 reactor 1 - reactor core 2 - steam generator 3 - pump 4 - reloading machine 5 - reactor vault 6 - cooling system... [Pg.2715]

In the future, electricity production at large NPPs is likely to remain the main application of nuclear energy. This factor and the reduction of unit costs with increase in the power and number of nuclear units were the reasons for conceptual study of a 1,200 MWe lead-cooled fast reactor as a candidate basic component of a large-scale nuclear power mix. The BREST-OD-300 being developed as a prototype of the BREST-1200 reactor, their design and engineering features are largely similar, as may be seen from the data of Table 58.6 (ISTC 2001 Adamov et al. 1997). [Pg.2717]

Nuclear power complex with BREST-OD-300 reactor 1 - reactor 2 - turbine unit 3 -waste storage and treatment complex 4 - on-site nuclear fuel cycle complex... [Pg.2717]

BREST-OD-300 (Russian Federation) Bystriy Reactor Estestveimoy Bezopasnosti (Fast Reactor Natural Safety)... [Pg.5]


See other pages where BREST-OD is mentioned: [Pg.2717]    [Pg.2718]    [Pg.2718]    [Pg.6]    [Pg.9]    [Pg.11]    [Pg.12]    [Pg.14]    [Pg.16]    [Pg.18]    [Pg.22]    [Pg.24]    [Pg.28]    [Pg.30]    [Pg.32]    [Pg.34]    [Pg.36]    [Pg.38]    [Pg.40]    [Pg.42]    [Pg.44]    [Pg.46]    [Pg.48]    [Pg.50]    [Pg.52]    [Pg.54]    [Pg.56]    [Pg.58]    [Pg.60]    [Pg.62]    [Pg.64]    [Pg.66]    [Pg.68]    [Pg.70]    [Pg.72]    [Pg.74]    [Pg.76]    [Pg.78]    [Pg.80]    [Pg.84]   


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BREST-OD-300 reactor

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