CRITICAL FLOW PREDICTION MODELS FOR THE COOLANT AT SUPERCRITICAL PARAMETERS

Authors

DOI:

https://doi.org/10.20535/1813-5420.1.2021.242182

Keywords:

critical flow, critical flow rate, supercritical parameters, chocking characteristics, flow chocking

Abstract

An interest of the problems of various thermophysical and hydrodynamic phenomena in the nuclear industry, determined by the real application in the field of analysis of the accident scenarios related to the loss of coolant accident. For the generic super critical water reactor the meaning of the problem at the initial stage of the critical flow process, is the existing of the uncertainty in the accepting boundary conditions to predict the flow characteristics. The article provides an analytical review of existing approaches for describing the critical flow phenomenon of the medium and to focus on the current predictive models. A description of the physical nature of such a phenomenon is provided. The scope of consideration includes information from the literature for single and two-phase flow, taking into account their physical basis and the assumptions made. The task of the work was to analyze the information found and to evaluate and update the data on the application of the models to obtain the critical characteristic. It was supposed to highlight the physical aspects and peculiarities of this phenomenon, as applied to the coolant at supercritical parameters. To formulate important requirements to the representative critical flow model for the possibility of its use in the system codes for evaluation of the nuclear safety problems of promising fourth generation nuclear reactors.

References

Generation IV International Forum: A decade of progress through international cooperation, JE Kelly - Progress in Nuclear Energy, Elsevier 2014

Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs), TECDOC-1746, IAEA, 2014.

Y.Y. Bae, L.K.H. Leung, J.A. Lycklama À Nijeholt, M. Andreani, T. Schulenberg, J. Starflinger, Y. Ishiwatari, Y. Oka, H. Mori, and K. Ezato, "Status of ongoing research on SCWR thermal-hydraulics and safety", GIF Symposium, Paris, France, 2009

Fundamentals of Multiphase flow. Prof. M. L. Corradini. DEP, University of Wisconsin, USA, 1997

Critical flow models. State of art report on critical flow modeling. F. D’auria, P. Vigni, University of Pisa, Italy, 1980

Moody, Frederick J. Maximum discharge rate of liquid-vapor mixtures from vessels. USA, 1975

G. B. Wallis, "Critical two-phase flow," International Journal of Multiphase Flow, vol. 6, p. 97-112, 1980 Lahey K.T. Jr., Moody F.J., "The Thermal-hydraulics of a boiling water nuclear reactor", ANS Monograph,

p. 467, USA, 1977

F. J. Moody, Maximum Flow Rate of a Single Component, Two-Phase Mixture, J. Heat Transfer., 87(1):

-141, ASME, USA, 1965

Henry R. E, Fauske H.K. "The two phase critical flow of one component mixtures in nozzles, orifices and

short tubes", J. Heat Transfer, 93, p179, ANL , USA, 1971

Ransom V.H., Trapp J.A., "The Relap 5 choked flow model and application to a large scale flow test",

EG&G Idaho Inc., ASME, Saratoga, USA, 1980

Lee D H, Swinnerton D. Evaluation of critical flow for supercritical steam-water. EPRI-NP-3086, Final

report, USA, 1983

Mignot G, Anderson M, Corradini M. Initial Study of Supercritical Fluid Blowdown, Fusion Science and

Technology, 47:3, 574-578, USA, 2007

Critical Flow Experiment And Analysis For Supercritical Fluid, Guillaume Mignot, Mark Anderson And

Michael Corradini, Nuclear Engineering and Engineering Physics Department, University of Wisconsin, 1500 engineering Drive, Madison, WI, 53706 USA, 2007

Experimental study of critical flow of water at supercritical pressure, Y Chen, C Yang, S Zhang, M Zhao, K Du - Frontiers of Energy, 2009

The SCDAP/RELAP5-3D© Code Development Team. SCDAP/RELAP5-3D© code manual. INEEL/EXT- 02/00589, Idaho National Engineering and Environmental Laboratory, May 2002 ( http://www.inel.gov/relap5).

Published

2021-10-11

Issue

Section

TECHNOLOGIES AND EQUIPMENT IN ENERGY