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http://dx.doi.org/10.5516/NET.2007.39.5.627

ASSESSMENT OF STABILITY MAPS FOR HEATED CHANNELS WITH SUPERCRITICAL FLUIDS VERSUS THE PREDICTIONS OF A SYSTEM CODE  

Ambrosini, Walter (Universita di Pisa, Dipartimento di Ingegneria Meccanica Nucleare e della Produzione Via Diotisalvi)
Sharabi, Medhat Beshir (Universita di Pisa, Dipartimento di Ingegneria Meccanica Nucleare e della Produzione Via Diotisalvi)
Publication Information
Nuclear Engineering and Technology / v.39, no.5, 2007 , pp. 627-636 More about this Journal
Abstract
The present work is aimed at further discussing the effectiveness of dimensionless parameters recently proposed for the analysis of flow stability in heated channels with supercritical fluids. In this purpose, after presenting the main motivations for the introduction of these parameters in place of previously proposed ones, additional information on the theoretical bases and on the consequences of this development is provided. Stability maps, generated by an in-house program adapted from a previous application to boiling channels, are also shown for different combinations of the operating parameters. The maps are obtained as contour plots of an amplification parameter obtained from numerical discretization and subsequent linearization of governing equations; as such, they provide a quantitatively clear perspective of the effect of different boundary conditions on the stability of heated channels with supercritical fluids. In order to assess the validity of the assumptions at the basis of the in-house model, supporting calculations have been performed making use of the RELAP5/MOD3.3 computer code, detecting the values of the dimensionless parameters at the threshold for the occurrence of instability for a heated channel representative of SCWR proposed core configurations. The obtained results show reasonable agreement with the maps, supporting the applicability of the proposed scaling parameters for describing the dynamic behaviour of heated channels with supercritical fluids.
Keywords
SCWR; Supercritical Fluid; Stability; Heated Channels;
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1 Heusener, G., Mueller, U., Squarer, D., 2000, 'High performance light water reactor (HPLWR)', Nucl. Europe Worldscan XX (1/2), 59-60
2 Heusener, G., Mueller, U., Schulenberg, T., Squarer, D., 2000. 'European development program for a high performance light water reactor (HPLWR)', SCR-2000, The University of Tokyo, Tokyo, Japan
3 Yi, T.T., Koshizuka, S., and Oka, Y., 2004, 'A Linear Stability Analysis of Supercritical Water Reactors, (I) Thermal- Hydraulic Stability', Journal of Nuclear Science and Technology, Vol. 41, No. 12, p. 1166-1175 (December 2004)   DOI   ScienceOn
4 Yi, T.T., Koshizuka, S., and Oka, Y., 2004, 'A Linear Stability Analysis of Supercritical Water Reactors, (II) Coupled Neutronic Thermal-Hydraulic Stability', Journal of Nuclear Science and Technology, Vol. 41, No. 12, p. 1166-1175 (December 2004)   DOI   ScienceOn
5 Duffey R.B., Pioro I.L., 2005, Experimental heat transfer of supercritical carbon dioxide flowing inside channels (survey), Nuclear Engineering and Design, 235 (2005) 913-924   DOI   ScienceOn
6 Zhao, J., Saha, P., Kazimi, M.S., 2005, 'Stability of Supercritical Water-Cooled Reactor During Steady-State and Sliding Pressure Start-Up', The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11) Paper: 106 Popes' Palace Conference Center, Avignon, France, October 2-6, 2005
7 Pioro I.L., Duffey R.B., 2005, Experimental heat transfer in supercritical water flowing inside channels (survey), Nuclear Engineering and Design, 235 (2005) 2407-2430   DOI   ScienceOn
8 Ambrosini, W., Di Marco, P., Susanek, A., 1999, 'Prediction of Boiling Channel Stability by a Finite-Difference Numerical Method', 2nd International Symposium on Two-Phase Flow Modelling and Experimentation, Pisa, Italy, May 23-26, 1999
9 Ambrosini, W., 2007, 'On the Analogies in the Dynamic Behaviour of Heated Channels with Boiling and Supercritical Fluids', Nuclear Engineering and Design, Vol. 237/11 pp 1164-1174   DOI   ScienceOn
10 Squarer, D., Schulenberg, T., Struwe, D., Okab, Y., Bittermann, D., Aksan, N., Maraczy, C., Kyrki-Rajamaki, R., Souyri, A., Dumazh, P., 2003, 'High performance light water reactor', Nuclear Engineering and Design, vol. 221, pp 167-180   DOI   ScienceOn
11 SCIENTECH Inc., 1999, 'RELAP5/Mod3 Code Manual, Volume I: Code Structure, System Models and Solution Methods', The Thermal Hydraulics Group, Idaho, June 1999
12 Lahey R.T. and Moody F.J., 1993, The thermalhydraulics of a boiling water reactor, American Nuclear Society, 1993
13 Cheng X., and Schulenberg T., 2001, Heat Transfer at Supercritical Pressure – Literature Review and Application to an HPLWR, Scientific Rept. FZKA6609, Forschungszentrum Karlsruhe, Germany
14 Ortega Gomez T., Class A., Lahey R. T., Jr., Schulenberg T., 2006, Stability Analysis of a Uniformly Heated Channel with Supercritical Water, 14th International Conference on Nuclear Engineering (ICONE 14), Miami, Florida, USA, July 17-20, 2006
15 Chatoorgoon, V., 2001, 'Stability of supercritical fluid flow in a single-channel natural-convection loop', International Journal of Heat and Mass Transfer, 44 (2001) 1963-1972   DOI   ScienceOn
16 Ambrosini, W., Sharabi, M.B., 2006, 'Dimensionless Parameters in Stability Analysis of Heated Channels with Fluids at Supercritical Pressures', 14th International Conference on Nuclear Engineering (ICONE 14), Miami, Florida, USA, July 17-20, 2006
17 NIST Reference Fluid Thermodynamic and Transport Properties – REFPPRO, Aug. 2002., Lemmon, E.W., McLinden, M.O., Hurber, M.L. (Eds.), NIST Standard Reference Database 23 (Software and Source), V. 7.0, U.S. Department of Commerce
18 Dobashi, K., Oka, Y., Koshizuka, S., 1998, 'Conceptual design of a high temperature power reactor cooled and moderated by supercritical light water', Proceedings of the Sixth International Conference on Nuclear Engineering. ICONE6, ASME, NY
19 D'Auria F. (Editor) et al. 'State-of-the-art report on boiling water reactor stability', NEA/CSNI/R(96)21, OCDE/GD(97)13, OECD/NEA Paris, 1997
20 Zuber, N., 1966, 'An Analysis of Thermally Induced Flow Oscillations in the Near-Critical and Super-Critical Thermodynamic Region', Report NASA-CR-80609, Research and Development Center, General Electric Company, Schenectady, NY, USA, May 25, 159 pp
21 Ambrosini, W., Ferreri, J.C., 1998, 'The Effect of Truncation Error on Numerical Prediction of Stability Boundaries in a Natural Circulation Single-Phase Loop', Nuclear Engineering and Design, 183 (1998), pp. 53-76   DOI   ScienceOn