2024, Issue 1

EDN: HIGZKT

Authors & Affiliations

Anfimov A.M., Timin D.A.
Afrikantov Experimental Design Bureau for Mechanical Engineering, Nizhny Novgorod, Russia

Timin D.A. – Design Engineer 3^d Category. Contacts: 15, Burnakovsky proezd, Nizhny Novgorod, 603074. Tel.: +7 (831) 246-94-40; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Anfimov A.M. – Head of Group, Department for Physical and Thermal-Hydraulic Analyses of Stationary Reactor Plants.

Abstract

The article presents a computational analysis of the behavior of a three-circuit, three-loop BN reactor plant with an integral layout of the primary circuit and characteristics close to medium-sized plants under conditions of a primary circuit circulation break accident. A circulation break may occur as a result of primary circuit sodium flowing out of the reactor, causing the sodium level to drop below the inlet holes of the IHX. Termination of forced flow through the IHX causes a sharp decrease in heat removal from the reactor, which can result in reactor heatup.
The analysis of the dynamics of reactor heatup and subsequent cooldown under conditions of a primary circuit sodium circulation break is the subject matter of this work. Calculations were performed for several variants of the operating equipment configuration (cooldown through steam generators, through three ECDS loops).
Modeling the behavior of the BN reactor plant under conditions of a primary circuit sodium circulation break accident was conducted using the certified SOKRAT-BN code.
The results of studies on a primary circuit circulation break accident, taking into account various measures for its management, have shown:
1) In the event of reactor plant cooldown using three loops through the SG, the temperatures of the fuel cladding and reactor vessel do not reach the maximum allowable values.
2) In the event of reactor cooldown after the primary circuit circulation break by connecting the three ECDS loops, the power removed from the reactor core will not be enough to ensure its cooldown.

Keywords
safety analysis, sodium, computational studies, fast neutron, reactor plant, emergency cooldown system, air heat exchanger, core, intermediate heat exchanger, fuel assembly, circulation break

Article Text (PDF, in Russian)

References

UDC 621.039.586

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 1, 1:6