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Lead-cooled fast reactor (BREST) with an on-site fuel cycle
Lead-cooled fast reactor (BREST) with an on-site fuel cycle
2009
Yu. G. Dragunov
B. A. Gabaraev
V. N. Leonov
V. V. Orlov
V. S. Smirnov
V. S. Tsikunov
Yu.S. Cherepnin
Keywords:
energy source
Thermal power station
Radioactive waste
Lead-cooled fast reactor
Environmental science
Nuclear engineering
Coolant
Plutonium
Fission products
Enriched uranium
Correction
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