Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

DOI: 10.55176/2414-1038-2019-2-136-150

Authors & Affiliations

Toshinsky G.I. 1,2
1 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 JSC “AKME-engineering”, Obninsk, Russia

Toshinsky G.I. – Chief Researcher – Advisor to the General Director, Dr. (Techn.) Sci., professor, A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7(484) 399-84-13; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..


Development of reactor facilities (RF) with lead-bismuth coolant (LBC) was carried out in conditions of lack of necessary knowledge and experience. Moreover, there were fixed directive terms of work completion, which practically eliminated the opportunity for performance of related scientific and research works that was a reason of multiple failures at the stage of mastering of that technology. In the presented report the following issues are considered: the reasons for option of eutectic lead-bismuth alloy as coolant, principal scientific and technical problems solved in the process of mastering of LBC cooled RFs including the problem of coolant technology and corrosion resistance of steels, providing of radiation safety when realizing works related to release of polonium, providing of reliability of steam generators, incidents and accidents happened in the process of operating and ways for elimination of their reasons, experience of fuel unloading performance. On the whole, in the process of performing tests at Facility 27/VT the invaluable experience was obtained that made possible elimination of the reasons of happened accidents and provide reliable operation at RFs of serial nuclear submarines (NS) of Project 705 (705K). On the basis of critically analyzed operating experience, the civilian RF project, namely SVBR-100 that is meeting the Generation IV requirements is being developed.

lead-bismuth coolant, reactor, steam generator, polonium, accident, corrosion, operating experience, core

Article Text (PDF, in Russian)


UDC 621.039

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 2, 2:14