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

Year: 2010

Type: article

Abstract: 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.

Source: Atomic Energy

DOI: 10.1007/s10512-010-9284-1

Authors: O. M. Saraev, N. N. Oshkanov, A. V. Zrodnikov, V. M. Poplavskii, Yu. M. Ashurko, M. V. Bakanov, B. A. Vasiliev, Yu. L. Kamanin, V. N. Ershov, M. N. Svyatkin, A. S. Korolkov, Yu. M. Krasheninnikov

Institutions: Institute for Physics and Power Engineering, State Scientific Center - Research Institute of Atomic Reactors

Language: English

Topic: Nuclear reactor physics and engineering

Subfield: Nuclear Energy and Engineering

Field: Energy

Domain: Physical Sciences

Open Access status: diamond

OpenAlex ID: W2061702014

FWCI:

Cites: 1

Cited by: 5

Related to: 10