Abstract
A comparative analysis of the experimental data, which were obtained in a benchmark experiment on the thermohydraulics of a model assembly of fuel-element simulators in a flow of sodium-potassium alloy, and calculations performed by specialists, using thermohydraulic codes, from different countries is performed. The model assembly consisted of 25 fuel-element simulators arranged in a square. Russian specialists used the BRS-TVS.R code to perform calculations of the benchmark experiment, Japanese specialists used SPIRAL and AQUA, Spanish specialists used FLUENT, Dutch specialists used STAR-CD, and South Korean specialists used MATRA and CFX.
The following experimental and computational parameters were compared: the coolant temperature in the channels under nonuniform geometric and thermal conditions in the assembly, the surface temperature of the measuring fuel-element simulator on the heated section, and the coolant velocity in the assembly cells around the measuring simulator. Special attention was given to investigating the influence of the spacing lattice on the coolant velocity.
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REFERENCES
A. V. Zhukov, Yu. A. Kuzina, A. P. Sorokin, et al., “Experimental study on models of heat transfer in a lead-cooled core of a BREST-OD-300 reactor,” Teploenerget., No. 3, 2–10 (2002).
Yu. A. Kuzina and A. G. Sila-Novitskii, “Model experiments and calculations (TIGR-BRS code) on studying temperature and velocity fields in reactor cores with heavy coolant,” ibid., No. 11, 71–80 (2002).
Yu. A. Kuzina, A. V. Zhukov, A. P. Sorokin, et al., “Heat transfer and temperature fields in the core of a BREST reactor operating on fast neutrons and cooled with lead,” Izv. Vyssh, Ucheb. Zaved. Yad. Energet., No. 4, 91–99 (2002).
Yu. A. Kuzina, A. V. Zhukov, A. P. Sorokin, et al., “Results of measurements of the velocity fields by the electromagnetic method in model assemblies of the BREST-OD-300 reactor,” ibid., No. 1, 77–88 (2003).
V. P. Smirnov, A. I. Filin, A. G. Sila-Novitsky, et al., “Thermohydraulic research for the core of the BREST-OD-300 reactor,” in: Proceedings of the 11th International Conference on Nuclear Engineering, Tokyo, Japan (2003), No. ICONE11-36407.
Yu. A. Kuzina, A. V. Zhukov, M. V. Orekhov, et al., “Temperature field of fuel elements in the core of a BREST-OD-300 reactor (experiments performed on models),” in: Proceedings of a Scientific Session of the Moscow Engineering Physics Institute 2002, Moscow Engineering Physics Institute (2002), Vol. 8, pp. 48–49.
Yu. A. Kuzina, A. V. Zhukov, V. P. Smirnov, et al., “Measurement of velocity fields on model fuel assemblies for the BREST-OD-300 reactor core,” ibid., pp. 46–47.
Yu. A. Kuzina, V. P. Smirnov, and A. P. Sorokin, “Computational investigations for the thermohydraulic validation of the BREST-OD-300 reactor core,” ibid., pp. 44–45.
Yu. A. Kuzina, Thermohydraulic Simulation for BREST Reactor Core Validation, Camdidate's Dissertation in Engineering Sciences. State Science Center of the Russian Federation — Physics and Power-Engineering Institute, Obninsk (2003).
A. V. Zhukov, J. A. Kuzina, A. P. Sorokin, et al., “Specification of the benchmark problem ‘Hydraulics and heat transfer in the model pin bundles with liquid metal coolant’,” in: Meeting of International Working Group on Thermohydraulics of Advanced Nuclear Reactors, Obninsk, Russia, July 5–9, 2004, pp. 129–163.
D. A. Afremov, V. P. Smirnov, and D. A. Yashnikov, “Calculations using BRS-TVS.R code as a part of the standard problem ‘Hydraulics and heat exchange in model rod assemblies with liquid-metal cooling’ including uncertainty analysis,” ibid., pp. 164–187.
H. Ohshima and Y. Imai, “Thermal hydraulic analysis of model pin bundle with liquid metal coolant — simulation results of standard problem,” ibid., pp. 188–202.
A. Pena and G. Esteban, “Benchmark problem: hydraulics and heat transfer in the model pin bundles with liquid metal coolant UPV-EHU calculations,” ibid., pp. 238–250.
J. Carlsson and H. Wider, “Results of calculations of the standard problem ‘Hydrodynamics and heat transfer in a subassembly model cooled by liquid metal coolant’,” ibid., pp. 203–217.
H. Son and K. Suh, “Result of calculations of the standard problem hydraulics and heat transfer in a subassembly model cooled by liquid metal coolant,” ibid., pp. 218–237.
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Translated from Atomnaya Energiya, Vol. 99, No. 5, pp. 336–348, November, 2005.
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Zhukov, A.V., Kuzina, Y.A. & Sorokin, A.P. Analysis of a Benchmark Experiment on the Hydraulics and Heat Transfer in a Liquid-Metal-Cooled Assembly of Fuel-Element Simulators. At Energy 99, 770–781 (2005). https://doi.org/10.1007/s10512-006-0015-6
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DOI: https://doi.org/10.1007/s10512-006-0015-6