Browse > Article
http://dx.doi.org/10.1016/j.net.2016.06.007

Bubbly, Slug, and Annular Two-Phase Flow in Tight-Lattice Subchannels  

Prasser, Horst-Michael (ETH Zurich, Department of Mechanical and Process Engineering (D-MAVT))
Bolesch, Christian (ETH Zurich, Department of Mechanical and Process Engineering (D-MAVT))
Cramer, Kerstin (ETH Zurich, Department of Mechanical and Process Engineering (D-MAVT))
Ito, Daisuke (ETH Zurich, Department of Mechanical and Process Engineering (D-MAVT))
Papadopoulos, Petros (ETH Zurich, Department of Mechanical and Process Engineering (D-MAVT))
Saxena, Abhishek (ETH Zurich, Department of Mechanical and Process Engineering (D-MAVT))
Zboray, Robert (Paul Scherrer Institute, PSI)
Publication Information
Nuclear Engineering and Technology / v.48, no.4, 2016 , pp. 847-858 More about this Journal
Abstract
An overview is given on the work of the Laboratory of Nuclear Energy Systems at ETH, Zurich (ETHZ) and of the Laboratory of Thermal Hydraulics at Paul Scherrer Institute (PSI), Switzerland on tight-lattice bundles. Two-phase flow in subchannels of a tight triangular lattice was studied experimentally and by computational fluid dynamics simulations. Two adiabatic facilities were used: (1) a vertical channel modeling a pair of neighboring sub-channels; and (2) an arrangement of four subchannels with one subchannel in the center. The first geometry was equipped with two electrical film sensors placed on opposing rod surfaces forming the subchannel gap. They recorded 2D liquid film thickness distributions on a domain of $16{\times}64$ measuring points each, with a time resolution of 10 kHz. In the bubbly and slug flow regime, information on the bubble size, shape, and velocity and the residual liquid film thickness underneath the bubbles were obtained. The second channel was investigated using cold neutron tomography, which allowed the measurement of average liquid film profiles showing the effect of spacer grids with vanes. The results were reproduced by large eddy simulation + volume of fluid. In the outlook, a novel nonadiabatic subchannel experiment is introduced that can be driven to steady-state dryout. A refrigerant is heated by a heavy water circuit, which allows the application of cold neutron tomography.
Keywords
Computational Fluid Dynamics; Subchannel Flow; Tight Fuel Rod Lattice; Tomography; Two-Phase Flow; Void Fraction;
Citations & Related Records
연도 인용수 순위
  • Reference
1 Y. Fukaya, T. Okubo, S. Uchikawa, Investigation on spent fuel characteristics of reduced-moderation water reactor (RMWR), Nucl. Eng. Des 238 (2008) 1601-1611.   DOI
2 W. Liu, A. Ohnuki, H. Yoshida, M. Kureta, K. Takase, H. Akimoto, Thermal feasibility analyses for the 1356MWe high conversion-type innovative water reactor for flexible fuel cycle, Heat Transfer Eng. 29 (8) (2008) 704-711.   DOI
3 JAEA, Reduced-Moderation Water Reactor (RMWR), Status Report 80, release 04.04, JAEA., 2011. Available from: https://aris.iaea.org/sites/..%5CPDF%5CRMWR.pdf.
4 R. Brogli, B. Kuczera, H. Moldaschl, W. Oldekop, Lessons learned from the PWHCR development, in: R. Chawla, R. Bohme, J. Dreier, R. Brogli, J. Axmann, H.D. Berger, C.H.M. Broeders, H. Hager, B. Kuczera, H. Moldaschl, W. Oldekop, S. Pelloni, N. Rouge, M. Schatz, R. Seiler, S. Yanar (Eds.), Contributions to Technical and Economic Aspects of High Converters, PSI-Bericht Nr. 71, Paul Scherrer Institut, June 1990, pp. 54-62.
5 J. Yamashita, F. Kawamura, T. Mochida, Next-generation nuclear reactor systems for future energy, Hitachi Rev. 53 (3) (2004) 131-135.
6 S. Uchikawa, T. Okubo, T. Kugo, H. Akie, R. Takeda, Y. Nakano, A. Ohunki, T. Iwamura, Conceptual design of innovativewater reactor for flexible fuel cycle (FLWR) and its recycle characteristics, J. Nucl. Sci. Technol. 44 (3) (2007) 277-284.   DOI
7 H. Tochihara, Y. Komano, M. Ishida, K. Narukawa, M. Umeno, Nuclear design for mixed moderator PWR, Prog. Nucl. Energ. 32 (314) (1998) 533-537.   DOI
8 D. Ito, M. Damsohn, H.-M. Prasser, M. Aritomi, Dynamic film thickness between bubbles and wall in a narrow channel, Exp. Fluids 51 (3) (2011) 821-833. Available from: http://link.springer.com/article/10.1007/s00348-011-1105-3.   DOI
9 M. Damsohn, H.-M. Prasser, High-speed liquid film sensor for two-phase flows with high spatial resolution based on electrical conductance, Flow Meas. Instrum. 20 (2009) 1-14.   DOI
10 D. Ito, H.-M. Prasser, Measurement of two-phase flow structure in a narrow rectangular channel, in: G.U. Beltran, L.L. Castro Gomez (Eds.), Flow Measurement, InTech, 2012, pp. 73-94.
11 M. Damsohn, H.-M. Prasser, Experimental studies of the effect of functional spacers to annular flow in subchannels of a BWR fuel element, Nucl. Eng. Des. 240 (2010) 3126-3144.   DOI
12 R. Zboray, J. Kickhofel, M. Damsohn, H.-M. Prasser, Coldneutron tomography of annular flow and functional spacer performance in a model of a boiling water reactor fuel rod bundle, Nucl. Eng. Des. 241 (2011) 3201-3215.   DOI
13 D. Ito, H.-M. Prasser, Spatio-temporal measurement of liquid film thickness in tight-lattice double subchannels, The 15th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, NURETH-15, Pisa, Italy, May 12-17, 2013, Paper NURETH15-226. Available from: http://www.ans.org.
14 P. Papadopoulos, Measurements in a Triangular Tight Lattice Channel with Mesh Sensors, Bachelor Thesis, ETH Zurich, Laboratory of Nuclear Energy Systems., 2011. Available from: hprasser@ethz.ch.
15 R. Zboray, H.-M. Prasser, Neutron imaging of annular flows in a tight lattice fuel bundle model, Nucl. Eng. Des. 262 (2013) 589-599.   DOI
16 A. Saxena, R. Zboray, H.-M. Prasser, Simulations and Measurements of Adiabatic Annular Flows in a Triangular, Tight Lattice Nuclear Fuel Bundle Model, Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation (CFD4NRS-5), OECD/NEA & IAEA Workshop, Zurich, Switzerland, September 9-11, 2014, paper S02-1. Available from: https://www.oecd-nea.org/nsd/csni/cfd.
17 M. Damsohn, Liquid films and droplet deposition in a BWR fuel element, PhD Thesis No. 19527, ETH Zurich., 2011. Available from: http://e-collection.library.ethz.ch/eserv/eth:2835/eth-2835-02.pdf.
18 A. Saxena, H.-M. Prasser, Liquid Film Modeling in BWR Subchannel with Spacers, Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation (CFD4NRS-5), OECD/NEA & IAEA Workshop, Zurich, Switzerland, September 9-11, 2014, paper S02-4. Available from: https://www.oecd-nea.org/nsd/csni/cfd.
19 K. Cramer, Investigation of the Influence of the Phase Transition on the Liquid Film Thickness in Vertical, Annular Two-phase Flow, Master thesis, ETH Zurich., April 2014. Available from: hprasser@ethz.ch.
20 R. Zboray, Ch. Bolesch, H.-M. Prasser, Neutron and X-ray imaging techniques for nuclear fuel rod bundle optimization and development, SWINTH-2016, Livorno, June 15-17, 2016, paper 17. Available from: hprasser@ethz.ch.