Operating experience and prospects for future development of sodium-cooled fast reactors

The main stages of the development of sodium-cooled fast reactors in Russia are described. The statistical information on the deviations from the normal regime of functioning that occur in BOR-60 and BN-600 operation is presented. The important role of BN-600 at the Beloyarskaya nuclear power plant...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2010-08, Vol.108 (4), p.240-247
Main Authors: Saraev, O. M., Oshkanov, N. N., Zrodnikov, A. V., Poplavskii, V. M., Ashurko, Yu. M., Bakanov, M. V., Vasiliev, B. A., Kamanin, Yu. L., Ershov, V. N., Svyatkin, M. N., Korolkov, A. S., Krasheninnikov, Yu. M.
Format: Article
Language:English
Subjects:
Analysis
Design engineering
Hadrons
Heavy Ions
Nuclear Chemistry
Nuclear Energy
Nuclear Physics
Nuclear power plants
Nuclear reactors
Physics
Physics and Astronomy
Sodium
Startups
Statistical analysis
Studies
Vacuum distillation
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Summary:The main stages of the development of sodium-cooled fast reactors in Russia are described. The statistical information on the deviations from the normal regime of functioning that occur in BOR-60 and BN-600 operation is presented. The important role of BN-600 at the Beloyarskaya nuclear power plant in the validation of sodium-cooled fast reactors is shown. A conclusion is drawn on the basis of a review of the operating experience about the level of mastery of sodium-cooled fast reactors in Russia and the prospects for further development of such reactors are analyzed taking account of this experience.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-010-9284-1