Authors & Affiliations

Beznosov A.V., Bokova T.A., Bokov P.A., Marov A.R., L'vov A.V., Volkov N.S.
Nizhniy Novgorod State Technical University n.a. R.E. Alekseev, Nizhniy Novgorod, Russia

Beznosov A.V. – Doctor of Technical Sciences, Professor, Department of ATS.
Bokova T.A. – Associate Professor, Department of ATS.
Bokov P.A. – Associate Professor, Department of ATS.
Marov A.R. – graduate student. Contact: 603155, Nizhny Novgorod, Mininst., 24 K1, 8 (920) 048-10-37, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
L’vov A.V. – engineer of the department "ATS".
Volkov N.S. – graduate student.

Abstract

The analysis and new scientific and technical solutions corresponding to the evolutionary development of low and medium power reactor plants with heavy liquid metal coolants are presented. The analysis was carried out on the basis of experience in the creation and operation of reactor installation with lead-bismuth coolant and research, primarily experimental, performed at the Nizhny Novgorod State Technical University (NSTU) in rationale of the small and medium-sized power plants developed at NNSTU reactor installation with horizontal steam generators (BRS-GPG). The paper substantiates the choice of coolant. With the proposed arrangement of the reactor loop, the maximum possible natural circulation is achieved, which significantly increases the safety of reactor installation. The results of studies (simulations) of one of the most potentially dangerous accidents in reactor installation with HLMC – "large steam generator leak" can qualitatively reduce the consequences of the accident when using the design of a horizontal steam generator in which the pipe system is placed with minimal burial of pipes under the level of HLMC, which eliminates the flow of water into the reactor core, re-pressurization of the reactor circuit, etc. It is probably advisable to consider the characteristics of the core, analog ary accepted for SVBR or BREST-OD-300. A system is proposed for cooling the reactor and providing the reactor installation shutdown modes, its characteristics are studied and tested at the NSTU stands.

Keywords
fast neutron reactor, heavy liquid metal coolant, BRS-GPG, steam generator, natural circulation, core.

Article Text (PDF, in Russian)

References

UDC 621.039.534

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2020, issue 1, 1:12