Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

DOI: 10.55176/2414-1038-2019-2-98-106

Authors & Affiliations

Petrochenko V.V., Grigoriev S.A., Dedul A.V., Komlev O.G., Kondaurov A.V.
JSC "AKME-engineering", Moscow, Russia

Petrochenko V.V. – Cand. Sci. (Tech.), Director General, JSC "AKME-engineering".
Grigoriev S.A. – Deputy General Director for Capital Construction, JSC "AKME-engineering".
Dedul A.V. – Deputy Director General — Chief Designer, Cand. Sci. (Tech.), JSC "AKME-engineering". Contacts: 13/1, Pyatnitskaya st., Moscow, Russia, 115035. Tel.: +7(919) 960-19-88; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Komlev O.G. – first deputy director general for production, Cand. Sci. (Tech.), JSC "AKME-engineering".
Kondaurov A.V. – first deputy of director general for development and international collaboration, JSC "AKME-engineering".


One of the key tasks for the reactor SVBR-100 project is substantiation of the core elements performance and efficiency. As part of the R & D program to justify the project, a significant amount of work was performed, which confirmed the corrosion resistance of the material of fuel rod claddings (ferric-martensitic (FM) steel) on the basis of 50 thousand hours, the consequences of deviations of the oxygen regime of the coolant from the optimal values were considered. Paper presents the main results of the analysis of fuel rod claddings loading conditions under normal operation, in violation of normal operating conditions and in conditions of hypothetical emergency overheating. It is concluded that the main mechanisms of damage to equipment and core elements in emergency and preemergency situations are associated with the degradation of strength properties with increasing temperature, while corrosion-erosion processes that accelerates with increasing temperature proceed relatively slowly and are limited in time of exposure. Based on the experimental data obtained in the justification of the SVBR project, the nature of the most dangerous emergency processes and the analysis of their consequences, the paper presents proposals for the formulation of key safety criteria for lead-bismuth reactor plants. The approach is based on the establishment of the maximum permissible temperature-time dependences and/or calculated residual deformations of fuel rod claddings made of FM steel.

SVBR-100 project, lifetime, fuel rod, lead-bismuth coolant, design limits

Article Text (PDF, in Russian)


UDC 621.039.54:621.039.58

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 2, 2:10