Optimization and Application of Analytical Model to Define Heat Carrier Parameters in T-Joints of Pipelines
Authors: Kurnosov M.M. | Published: 15.04.2015 |
Published in issue: #2(101)/2015 | |
Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
Keywords: T-joint, analytical model, numerical simulation, computational fluid dynamics (CFD), LES, sub-grid model, analytical model scaling |
Setting of the analytical model is executed to define the heat carrier local parameters in T-joints of the light-water reactor plants. The LES-type (large eddy simulation) turbulence model is used. Influence of such factors as sub-grid models, mesh resolution and in-time integration steps on the results is analyzed. Recommendations for parameters selection of computational model are specified. The estimation of possibility to scale computational models on geometric and operating parameters is carried out. Possibility to use the reduced analysis grids for defining time-averaged temperature and velocity of the jet flow in T-joints at constant Strouchal number, with mixing zone situated in branch pipe, is considered, too. Possibility of existence of low-frequency temperature variations in the liquid is shown. Calculations are performed on full-scale modes and geometric parameters.
References
[1] Kurnosov M.M., Strebnev N.A. Version of pre-test calculation of international mission on verification of CFD-codes based on experimental results obtained on the model of T-junction of pipelines. Sb. Voprosy atomnoy nauki i tekhniki, Obespechenie bezopasnosti AES [Collected articles "Problems of Atomic Science and Technology. Series "Organization of Nuclear Power Plant Safety], 2012, iss. 32, pp. 5-17 (in Russ.).
[2] Kurnosov M.M. Verification of computational model to define local parameters in T-junctions of pipelines. Tyazheloe mashinostroenie [Russian J. of Heavy Machinery], 2013, no. 10, pp. 37-40 (in Russ.).
[3] Mahaffy J. Synthesis of Results for the Tee-Junction Benchmark. Proc. of CFD4NRS-3, Washington State D.C., USA, 2010.
[4] Smith B., Mahaffy J., Angele K., Westin J. Report of the OECD/NEA-Vattenfall T-Junction Benchmark Exercise, OECD/NEA, Technical report, NEA/CSNI/R (2011) 5, 2011.
[5] Kurnosov M.M., Strebnev N.A. Optimization of the method to calculate local parameters in T-junctions of pipelines at turbulent pulsations. Sb. Voprosy atomnoy nauki i tekhniki. Obespechenie bezopasnosti AES [Collected articles "Problems of Atomic Science and Technology. Series "Organization of Nuclear Power Plant Safety], 2012, iss. 32, pp. 18-32 (in Russ.).
[6] Kolesnik V.P., Lyaskin A.S. Experience of ANSYS CFD complex application to solve problems of nuclear-power engineering . Problemy verifikatsii i primeneniya CFD-kodov v atomnoy energetike. Nauch.-tekhn. seminar GKAE "Rosatom". Sb. dokladov. OKBM [Problems of verification and CFD-codes application in nuclear-power engineering. Sci.-Tech. Seminar of State Corporation in Atomic Energetics "Rosatom". Collection of reports. Nizhniy Novgorod, 19-20.09.2012, pp. 113-122 (in Russ.).
[7] Loginov M.S., Comen E., Kuczaj A. Application of large-eddy simulation to pressurized thermal shock problem. Proc. ofICONE 17, ICONE 17-75894, Brussels, Belgium, 2009.
[8] ANSYS, Inc. ANSYS CFX-Solver Theory Guide, Release 12.1, 2009.
[9] Smagorinsky J. General circulation experiments with the primitive equations, Mon. Weather Review, 1963, vol. 93, pp. 99-165.
[10] Germano M., Piomelli U., Moin P., Cabot W. A dynamic subgrid-scale eddy viscosity mode. Phys. Fluids, 1991, no. A3(7), pp. 1760-1765.
[11] Lilly D.K. A proposed modification of the Germano subgrid-scale closure method. Phys. Fluids, 1992, no. A4(3), pp. 633-635.
[12] Nicoud F., Ducros F. Subgrid-scale stress modeling based on the square of the velocity gradient tensor. Flow, Turbulence and Combustion, 1999, vol. 62, pp. 183-200.
[13] Tanaka M., Ohshima H. Numerical simulation of thermal mixing in T-junction piping system using large-eddy simulation approach. Proc. of CFD4NRS-3,Washington State D C., USA, 2010.
[14] Parras F., Bosser M., Milan D., Berthollon G. Heat transfer in pressurized water reactor components most often subjects to thermal shock. Nuclear Technology, Jan. 1980, vol. 47, pp. 125-151.
[15] Khudson D. Statistika dlya fizikov. Lektsii po teorii veroyatnostey i elementarnoy statistike [Lections on probability theory]. Russ. Ed. Moscow, Mir Publ., 1970. 296 p.
[16] Sudakov A.V., Slovtsov S.V., Prokhorov V.A., Kashirin V.I., Fedosov V.G. Computational-experimental research of crack formation in the reactor equipment elements at temperature pulsations. Mat. 8 Mezhdunar. nauch.-tekhn. konf. "Obespechenie bezopasnosti AES s VVER" [Proc.8. Int. Sci. Conf. "Safety ensuring of atomic station with water-cooled power reactor"], Podol’sk, 28-31.05.2013 (in Russ.).