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Application of CFD and nodal expansion method for simulation and analysis of boron dilution accident.

Authors :
Kolali, Ali
Ghafari, Mohsen
Vosoughi, Naser
Source :
Annals of Nuclear Energy. Apr2024, Vol. 198, pN.PAG-N.PAG. 1p.
Publication Year :
2024

Abstract

• The malfunction of boron injection system is one transients affecting the characteristics of cooling fluid. • A realistic approach based on the CFD and nodal expansion method is employed for simulation of this accident. • The utilization of CFD method depicted the boron heterogeneous distribution effects. • Due to the reduction of the absorber in a part of the reactor core DNBR is close to the critical value of 1. Nuclear power, as a low-carbon energy source, provides the steady and reliable electricity. In this power source, safe operation plays a significant role from the point of view of design and economic cost. While nuclear power plants are designed to be safe in their operation and safe in the event of any malfunction or accident, some accidents with considerable occurrence frequency should be considered to provide related safety system and operation. The malfunction of boron injection system is one of this accident affecting the chemical and neutronic characteristics of cooling fluid. The aim of this study is the simulation and analysis of the boron dilution accident as one of Design Basis Accident, by considering the heterogeneous distribution of boron. For this purpose, CFD methods were used for exact evaluation of the boron distribution in each fuel assembly. Also, cross-section correction module and core calculation module are respectively developed by a cell calculation code and nodal expansion method. These modules are employed to apply absorber effects including boron and control banks and calculate 3D relative power. The results reveal the effect of heterogeneous distribution of boron in reactor pressure vessel and non-uniform chemical characteristics of coolant across fuel channels. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
03064549
Volume :
198
Database :
Academic Search Index
Journal :
Annals of Nuclear Energy
Publication Type :
Academic Journal
Accession number :
174759810
Full Text :
https://doi.org/10.1016/j.anucene.2023.110296