Universal correlations for predicting complete pump performance chracteristics

• Autorzy: Lahssuny Y. , Jędral W.
• Języki publikacji: EN

Abstrakty

EN

The aim of this paper is to introduce a systematic approach for the prediction of pump performance characteristics of different specific speeds when the experimental data are not available. To accomplish this task, a set of equations representing the best fits of the available experimental data is developed. The equations provide a data source useful in the design, simulation and checking of the pumps. The correlations obtained should avoid carrying out complex experimental programs in a test loop. Numerical results indicated that the proposed method favorably predicted the nuclear-grade coolant pump performance at minimal cost. Application of the method has demonstrated its viability as a tool of obtaining pump data useful to light water reactor safety analysis codes.

Słowa kluczowe

EN

pumps; pump performance characteristics

PL

pompy

• Wydawca: Oficyna Wydawnicza Politechniki Warszawskiej
• Czasopismo: Biuletyn Instytutu Techniki Cieplnej Politechniki Warszawskiej
• Rocznik: 2004
• Tom: nr 89/90
• Strony: 15--24
• Opis fizyczny: Bibliogr. 17 poz., tab., wykr.

Twórcy

autor

Lahssuny Y.

• Institute of Heat Engineering

autor

Jędral W.

• Institute of Heat Engineering

Bibliografia

• [1] Donsky В.: Complete pump characteristics and the effects of specific speeds on hydraulic transients. Journal of Basic Engineering, Transactions of the ASME, pp. 685-699, December, 1961.
• [2] Geffraye G., Beston D.: Assessment of the CATHARE ID pump model. Nuclear Engineering and Design, vol. 149, pp. 117-128, 1994.
• [3] Lahssuny Y.M., Jędral W.: A model for predicting nuclear reactor coolant pump behavior during normal and abnormal operating conditions. Proceedings Of The Third International Thermal Energy Congress, pp. 231-236, Marrakesh, Morocco, 9-12 June, 1997.
• [4] Lahssuny Y.M., Jędral W.: Universal representation of impeller pump characteristics and its importance to thermal-hydraulic codes. Proceedings of the Second International Thermal Energy Congress, pp. 637-642, Agadir, Morocco, June, 1995.
• [5] Lahssuny Y.M. et al.: Transients caused by pump coastdown in pressurized water reactors. Proceedings of the Fourth Arab Conference on the Peaceful Uses of Atomic Energy, vol. 2, pp. 81-98, AAEA, Tunis, April, 2000.
• [6] Lih-Yih Liao: Study and application of boiling water reactor jet pump characteristics. Nuclear Engineering and Design, vol. 132, pp. 339-350, 1992.
• [7] Loomis G.G.: Intact loop pump performance during the semiscale MOD-1 isothermal test series. Aerojet Nuclear Company, ANCR-1240, October, 1975.
• [8] More K.V., Rettig W.H.: RELAP4: A computer program for transient thermal-hydraulic analysis. Aerojet Nuclear Company, ANCR-1127, December, 1973.
• [9] Olson D.J.; Modeling philosophy and selection of pumps for use in small blowdown experiments. Topical Meeting on Water Reactor Safety, pp. 758-766, CONF-730304, March, 1973.
• [10] Olson D.J.: Single and two-phase performance characteristics of the MOD-1 semiscale pump under steady state and transient fluid conditions. Aerojet Nuclear Company, ANCR-1165, October, 1974.
• [11] Reactor coolant pump integrity in LOCA, Topical report, Westinghouse Electric Corporation, Nuclear Energy Systems, WCAP-8163, September, 1973.
• [12] RELAP5/MOD3: User's guidelines. Idaho National Engineering Laboratory, NUREG/CR-5535 & EGG-2596, vol. 5, January, 1992.
• [13] Stepanoff A.J.: Centrifugal and axial flow pumps. 2nd ed., John Wiley & Sons, Inc., New York 1957.
• [14] Streeter V.L., Wylie E.B.: Transient analysis of offshore loading systems. Journal of Engineering for Industry, Transactions of the ASME, pp. 259-265, February, 1975.
• [15] Streeter V.L., Wylie E.B.: Hydraulic transients. McGraw-Hill, 1967.
• [16] Sulzer centrifugal pump handbook. Elsevier Applied Science Publishers LTD. London 1992.
• [17] TRAC-PF1/MOD1: An advanced best-estimate computer program for P.W.R. thermal-hydraulic analysis. Los Alamos National Laboratory, NUREG/CR-3858, July, 1986.