Computational Thermofluid Dynamics in Rod Bundles of Liquid Metal Reactor

The Battery Omnibus Reactor Integral System (BORIS) is being developed as a multipurpose integral optimized fast reactor with an ultra long life core. BORIS is operated by natural circulation of the primary system lead (Pb) coolant without pump power. BREST is a liquid metal reactor with rod bundles in square arrangement. Its mockup test section contains one spacer grid located near the midplane of the rod bundle. These bundles have two zones. The rod diameters and heat production differ between the two zones. The experiment served as a standard thermal and hydraulic problem. This study focuses on thermohydrodynamics in the primary system of liquid metal cooled reactor utilizing the computational fluid dynamics (CFD) code CFX