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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)
  • Published : 2007.10.30

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

References

  1. 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
  2. Heusener, G., Mueller, U., Squarer, D., 2000, 'High performance light water reactor (HPLWR)', Nucl. Europe Worldscan XX (1/2), 59-60
  3. 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
  4. Cheng X., and Schulenberg T., 2001, Heat Transfer at Supercritical Pressure – Literature Review and Application to an HPLWR, Scientific Rept. FZKA6609, Forschungszentrum Karlsruhe, Germany
  5. 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 https://doi.org/10.1016/S0029-5493(02)00331-X
  6. 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
  7. Lahey R.T. and Moody F.J., 1993, The thermalhydraulics of a boiling water reactor, American Nuclear Society, 1993
  8. 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
  9. 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
  10. 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 https://doi.org/10.1016/S0017-9310(00)00218-0
  11. 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) https://doi.org/10.3327/jnst.41.1166
  12. 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) https://doi.org/10.3327/jnst.41.1166
  13. 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
  14. 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
  15. 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 https://doi.org/10.1016/j.nucengdes.2007.01.006
  16. 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
  17. SCIENTECH Inc., 1999, 'RELAP5/Mod3 Code Manual, Volume I: Code Structure, System Models and Solution Methods', The Thermal Hydraulics Group, Idaho, June 1999
  18. 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
  19. 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 https://doi.org/10.1016/S0029-5493(98)00157-5
  20. 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 https://doi.org/10.1016/j.nucengdes.2005.05.034
  21. 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 https://doi.org/10.1016/j.nucengdes.2004.11.011