Authors & Affiliations
Krapivtsev V.G., Markov P.V., Solonin V.I., Getya S.I.
Bauman Moscow State Technical University, Moscow, Russia
Markov P.V. — Associate Professor, Cand. Sci. (Tech.). Contacts: 5, building 1, 2-ya Baumanskaya st., Moscow, 105005, Russia. Tel.: +7 (499) 263-60-73; e-mail:
Solonin V.I. – Professor, Dr. Sci. (Tech.).
Krapivtsev V.G. – Associate Professor, Cand. Sci. (Tech.).
Getya S.I. – Senior Lecturer.
Abstract
The feature of hydrodynamics and heat transfer in the core of the BREST-OD-300 reactor consists in the application of fuel assemblies with fuel rod’s bundles with the same number and fuel rod pitch in a triangular lattice, but different fuel rod’s diameters; this feature makes the investigations of fluid dynamics and heat and mass transfer in these fuel rods bundles relevant. To study the characteristics of fluid flow and mass transfer in BREST-OD-300 fuel rods bundles at the Department of Nuclear Reactors (BMSTU) ware developed models of fuel assemblies containing 37 rods. The measurement results were obtained by creating a flow at the entrance to the support grid by an input device that creates a boundary layer at the surface of the cover with a thickness commensurate with the dimensions of the peripheral cells of the rod bundles. Experimental studies of the distribution of the fluid axial velocity and temperature in rods bundles are carried out. The pressure drop coefficients of spacer grids are determined. The influence of the geometry of spacer grids, boundary layers on the surface of model's shell on the flow and mass transfer in the fuel rods bundles of the layout is analyzed.
Keywords
fuel assembly, aerodynamic experiment, fuel rods of two diameters, cellular spacer grids, support grid, fuel assembly shell, inlet device, linear flow heater, combined measuring probe, velocity distributions, temperature distributions, static pressure, hydraulic losses, pessure-drop coefficients, Reynolds number
Article Text (PDF, in Russian)
UDC 621.039.519
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 1, 1:18