Modeling of Liquid Entrainment and Vapor Pull-Through in Header-Feeder Pipes of CANDU

  • Published : 2004.04.01

Abstract

The liquid entrainment and vapor pull-through offtake model of RELAP5/MOD3 had been developed for SBLOCA (Small Break Loss of Coolant Accident). The RELAP5/MOD3 model for horizontal volumes accounts for the phase separation phenomena and computes the flux of mass and energy through a branch when stratified conditions occur in the horizontal pipe. In the case of CANDU reactor, this model should be used in the coolant flow of 95 feeders connected to the reactor header component under the horizontal stratification in header. The current RELAP5 model can treat the only 3 directions junctions; vertical upward, downward, and side oriented junctions, and thus improvements for the liquid entrainment and vapor pull-through model were needed for considering the exact angles. The RELAP5 off-take model was modified and generalized by considering the geometric effect of branching angles. Based on the previous experimental results, the critical height correlation was reconstructed by use of the branch line connection angle and validation analyses were also performed using SET. The new model can be applied to vertical upward, downward and angled branch, and the accuracy of the new correlations is more improved than that of RELAP5.

Keywords

References

  1. B.D.Chung, et aI, 'Development of Best Estimate Auditing Code for CANDU Thermal-Hydraulic Safety Analysis,' KAERI/CR129/2002, KINSIHR-436, (2002)
  2. B.D.Chung et.al, 'Development of Preliminary PIRT (Phenomena Identification and Ranking Table) of Thermal-Hydraulic Phenomena for 330Mwt SMART Integral Reactor,' KAERI/TR-912/97, September (1997)
  3. B.N. Hanna ' CATHENA MOD-3.5/Rev 0 ; Theoretical Manual,' RC-982-3, COG-93-140 Rev 0.0, AECL, Whiteshell Lab.(1995)
  4. Zuber, N., 'Problems in Modeling of Small Break LOCA,' Nuclear Regulatory Commission Report, NUREG-0724 (1980)
  5. C. Smoglie, 'Two-Phase Flow Through Small Branches in a Horizontal Pipe with Stratified Flow, KfK 3861, Kernforschungszentrum Karlsruhe GmbH (KfK), Karlsruhe, FRG, December (1984)
  6. V. E. Schrock, S. T. Revankar, R. Mannheiner, and C. H. Wang, 'Small Break Critical Discharge -The Role of Vapor and Liquid Entrainment in a Stratified Two-Phase Region Upstream of the Break,' NUREG/CR-4761, LBL-22024, Lawrence Berkeley Laboratory, December (1986)
  7. Yonomoto, T. and Tasaka, K., 'New Theoretical Model for Two-Phase Flow Discharged from Stratified Two-Phase Flow Discharged from Stratified Two-Phase Region Through Small Break,' J. NucI.Sci.Tech., 25, 441-455 (1988) https://doi.org/10.3327/jnst.25.441
  8. Yonomoto, T. and Tasaka, K., 'Liquid and Gas Entrainment to Small Break Hole from a Stratified Two-Phase Region,' Int. J. Multiphase Flow, 17,745-765 (1991) https://doi.org/10.1016/0301-9322(91)90054-7
  9. T. Maciaszek and A. Menponteil, 'Experimental Study on Phase Separation in a Tee Junction for Steam-Water Stratified Inlet Flow,' Paper C2, European Two-Phase Flow Working Group Meeting, Munich, FRG, June 10-13, (1986)
  10. Thermal Hydraulics Group 'RELAP5/MOD3 Code Manual Volume 4 : Models and Correlations,' Scientech, Inc. , NUREG/CR-5535 (1998)
  11. Craya, A., 'Theoretical Research in the flow of Non-Homogeneous Fluids,' La Houille Blanche, pp. 44-55, January-February (1949)
  12. Armstrong,K.F., et aI., 'Theoretical and Experimental Study of the Onset of Liquid Entrainment During Dual Discharge from Large Reservoirs,' Int. J. Multiphase Flow, 18,217-227 (1992) https://doi.org/10.1016/0301-9322(92)90084-T
  13. Ibrahim G.Hassan, Hassan M. Soliman, Grant E. Sims and Janusz E. Kowalski, 'The Onset of Liquid Entrainment during Discharge from Two Branches on an Inclined Wall,' The Canadian Journal of Chemical Engineering, Volume 77, June, (1999)
  14. Milne-Thomson, L.M., 'Theoretical Hydrodynamics,' 5th Ed., MacMillan and Company Ltd., London, UK (1968)
  15. J. L. Anderson and R. L. Benedetti, 'Critical Flow Through Small Pipe Breaks,' EPRI NP-4532, Idaho National Engineering Laboratory, May (1986)
  16. T.S.Andreychek, et aI, 'Loss of RHRS cooling while the RCS is partially filled,' WCAP-11916, July (1988)
  17. Anderson, J. L. and Owca, W. A., 'Data Report for the TPFL Tee/Critical Flow Experiments, ' NUREG/CR-4164, EGG-2377, November (1985)
  18. S.H.Lee, et al 'Evaluation of Thermal Hydraulic Safety Analysis Computer Code System for CANDU Reactor,' KINS/GR-057 (1993), KINS/GR-077 (1994), KINS/GR-100 (1995), KINS/GR-111 (1996)
  19. Thermal Hydraulics Group 'RELAP5/MOD3 Code Manual Volume 1 : Code Structure, System Models, and Solution Methods,' Scientech, Inc. , NUREG/CR-5535 (1998)