Authors & Affiliations
Anfimov A.M., Kirilov I.N.
Afrikantov Experimental Design Bureau for Mechanical Engineering, Nizhny Novgorod, Russia
Anfimov A.M. – Head of Group.
Kirilov I.N. – Design Engineer 1st, Department for Physical and Thermal-Hydraulic Analyses of Stationary Reactor Plants. Contacts: 15, Burnakovsky proezd, Nizhny Novgorod, 603074. Tel.: +7 (831) 246-94-40; e-mail:
Abstract
The article presents the results of the computational analysis of an accident with complete instantaneous blockage of the flow area at the inlet of one fuel assembly of a BN reactor plant. The computational analysis of this accident is necessitated by the requirements of NP-18-05 “Requirements for the Contents of the Report on Safety Justification of Nuclear Power Plants with Fast Neutron Reactors”.
The computational analysis of the main processes under accident conditions with complete blockage of the flow area of one fuel assembly was conducted using the certified SOCRAT-BN code. The core nodalization diagram permits, on conservative assumptions, taking into account the main features of damage propagation from a damaged fuel assembly to neighboring ones.
The purpose of this work is to determine the accident phenomenology and to preliminarily estimate the core damage extent.
The article presents the main results of calculating the accident with flow area blockage of one BN reactor plant maximum stressed fuel assembly and estimates the timing of various stages of the accident process and the core damage extent.
As a result of analysis of the calculation results, it was established that damage to the core is limited to 7 fuel assemblies.
In the future, it is planned to refine the analysis results taking into account the assessment of the influence of errors and uncertainties on the calculation results.
Keywords
safety analysis, reactor plant, sodium, flow area blockage accident, sodium-cooled fast neutron reactor (BN), fuel assembly (FA), sodium boiling, fuel meltdown, fuel rod
Article Text (PDF, in Russian)
UDC 621.039.51
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 1, 1:4