Impact of spacer on inter sub-channel mixing of coolant in nuclear fuel bundle: a survey and future patterns of research and advances

References

1 Jayanti, S.; Reddy, R. K.: Effect of spacer grids on CHF in nuclear rod bundles. Nuclear Engineering and Design261 (2013) 66–7510.1016/j.nucengdes.2013.03.044Suche in Google Scholar

2 Verma, S. K.; Sinha, S. L.; Chandraker, D. K.: Experimental investigation of effect of spacer on single phase turbulent mixing rate on simulated subchannel of Advanced Heavy Water Reactor. Annals of Nuclear Energy110 (2017) 186–19510.1016/j.anucene.2017.06.020Suche in Google Scholar

3 Chandraker, D. K.: Study on critical power for Advanced Heavy Water Reactor. Ph.D. Thesis, Department of Nuclear Engineering, Tokyo Institute of Technology (2012)Suche in Google Scholar

4 Waters, E. D.: Fluid mixing experiments with a wire wrapped 7-rod bundle fuel assembly. Annular Space, 1961Suche in Google Scholar

5 Carelli, M.; Curzio, G.; Renieri. A.: A radioactive tracer technique for measuring coolant mixing in nuclear reactor fuel sub-assemblies. Nuclear Engineering and Design11 (1969) 93–10210.1016/0029-5493(70)90021-XSuche in Google Scholar

6 Cha, J. H.; Cho, M. H.: A study on coolant mixing in multi rod bundle subchannels. Journal of the Korean Nuclear Society2 (1970) 19–25Suche in Google Scholar

7 Roidt, M.; Vegter, B. J.; Pechersky, M. J.; Markley, R. A.: Experimental determination of turbulent exchange coefficients in a model reactor rod bundle. In: National heat transfer conference, Atlanta, Georgia, USA, number CONF-730803-2, 1973Suche in Google Scholar

8 Hanson, A. S.; Todreas, N.: Fluid mixing studies in a hexagonal 61-pin, wire wrappedrod bundle. Fuel Assem, 197710.2172/5159920Suche in Google Scholar

9 Rehme, K.: Turbulent momentum transport in rod bundles. Nuclear Engineering andDesign62 (1980) 137–146, 10.1016/0029-5493(80)90025-4Suche in Google Scholar

10 Rehme, K.: The structure of turbulent flow through rod bundles. Nuclear Engineeringand Design99 (1987) 141–15410.1016/0029-5493(87)90116-6Suche in Google Scholar

11 Rehme, K.: Experimental observations of turbulent flow through subchannels of rod bundles. Experimental Thermal and Fluid Science2 (1989) 341–34910.1016/0894-1777(89)90023-XSuche in Google Scholar

12 Rehme, K.: The structure of turbulence in rod bundles and the implications onnatural mixing between the subchannels. International Journal of Heat and Mass Transfer35 (1992) 567–58110.1016/0017-9310(92)90291-YSuche in Google Scholar

13 Ylönen, A.; Bissels, W.-M.; Prasser, H.-M.: Single-phase cross-mixing measurements in a 4 × 4 rod bundle. Nuclear Engineering and Design241 (2011) 2484–249310.1016/j.nucengdes.2011.04.014Suche in Google Scholar

14 Bulk, F. P.: An experimental study on cross-flow mixing in a rod-bundle geometry using a wire-mesh. Master's thesis, Delft University of Technology, 2012Suche in Google Scholar

15 Wang, X.; Wang, R.; Du, S.; Chen, J.; Tan, S.: Flow visualization and mixing quantification in a rod bundle using Laser induced fluorescence. Nuclear Engineering and Design305 (2016) 1–810.1016/j.anucene.2015.12.029Suche in Google Scholar

16 Sharma, M. P.; Nayak, A. K.: Determination of turbulent mixing rate for single-phase flow in simulated subchannels of a natural-circulation pressure tube-type BWR. Nuclear Science and Engineering180 (2015) 1–10, 10.13182/NSE14-102Suche in Google Scholar

17 Chandraker, D. K.; Nayak, A. K.; Vijayan. P. K.: Effect of spacer on the dryout of BWR fuel rod assemblies. Nuclear Engineering and Design294 (2015) 262–27310.1016/j.nucengdes.2015.09.004Suche in Google Scholar

18 Kawahara, A.; Sadatomi, M.; Imamura, S.; Shimoharai, Y.; Hirakata, Y.; Endo, M.: Effects of grid spacer with mixing vane on entrainments and depositions in two-phase annular flows. Nuclear Engineering and Technology147 (2015) 389–39710.1016/j.net.2015.04.002Suche in Google Scholar

19 Cho, H.; Choi, K. K. Y.; ChoS. C.; Song. C. H.: Experimental observation of the droplet size change across a wet grid spacer in a 6X6 rod bundle. Nuclear Engineering and Design241 (2011) 4649–465610.1016/j.nucengdes.2011.03.042Suche in Google Scholar

20 Zhang, H.; Yokomine, T.; Kunugi, T.: Turbulence modulation of the upward turbulent bubbly flow in vertical ducts. Nuclear Engineering and Technology47 (2015) 513–52210.1016/j.net.2015.04.006Suche in Google Scholar

21 Michiyoshi, I.; Serizawa, A.: Turbulence in two-phase bubble flow. Nuclear Engineering and Design95 (1986) 253–26710.1016/0029–5493(86)90052-XSuche in Google Scholar

22 Serizawa, A.; Kataoka, I.: Turbulence suppression in bubbly two-phase flow. Nuclear Engineering and Design122 (1990) 1–1610.1016/0029-5493(90)90193-2Suche in Google Scholar

23 Whalley, P. B.: The calculation of dryout in a rod bundle. Int. J. Multiphase Flow3 (1977) 501–51510.1016/0301-9322(77)90026-XSuche in Google Scholar

24 Adamsson, C.; Le Corre, J. M.: Modeling and validation of a mechanistic tool (MEFISTO) for the prediction of critical power in BWR fuel assemblies. Nuclear Engineering and Design241 (2011) 2843–285810.1016/j.nucengdes.2011.01.033Suche in Google Scholar

25 Ishii, M.: Grolmes, M. A.: Inception criteria for droplet entrainment in two-phase concurrent film flow. AICHE J.21 (1975) 308–31810.1002/aic.690210212Suche in Google Scholar

26 Yang, S. K.; Chung, M. K.: Spacer grid effects on turbulent flow in rod bundles. Journal of Korean Nuclear Society28 (1996)Suche in Google Scholar

27 Rogers, J. T.; Tahir, A. E. E.: Turbulent interchange mixing in rod bundles and the role of secondary flows. ASME 75-HT-31, (1975)Suche in Google Scholar

28 Cheng, S. K.; Todreas, N. E.: Hydrodynamic models and correlations for bare and wire-wrapped Hexagonal rod bundles–bundle friction factors, sub-channel friction factors and mixing parameters. Nuclear Engineering and Design92 (1986) 227–25110.1016/0029-5493(86)90249-9Suche in Google Scholar

29 Yamamoto, Y.; Hoshide, A.; Mitsutake, T.; Morooka, S.: Analytical study on effects of BWR fuel spacer on dropletdeposition. Nuclear Engineering and Design175 (1997) 119–12910.1016/S0029-5493(97)00168-4Suche in Google Scholar

30 Rowe, D. S.: Measurement of turbulent velocity, intensity and scale in rod bundle flow channels. Pacific Northwest Laboratory, Wash., BNWL-1736 (1973) 10.2172/4435397Suche in Google Scholar

31 Kried, D. L.; Creer, J. M.; Bates, J. M.; Quigley, M. S.; Sutey, A. M.; Rowe, D. S.: Fluid flow measurements in rod bundles using laser Doppler anemometry techniques. Fluid Flow and Heat Transfer Over Rod or Tube Bundles, ASME, New York, 1979, pp. 13–27Suche in Google Scholar

32 Carajilescov, P.; Todreas, N. E.: Experimental and analytical study of axial turbulent flows in an interior sub channel of a bare rod bundle. J. Heat Transfer, Trans. ASME98 (1976) 262–26810.1115/1.3450529Suche in Google Scholar

33 Bartzis, J. G.; Todreas, N. E.: Turbulence modelling of axial flow in a bare rod bundle. J. Heat Transfer, Trans. ASME101 (1979) 628–63410.1115/1.3451048Suche in Google Scholar

34 Chieng; C.-C.; Lin, C.: Velocity distribution in the peripheral subchannels of the CANDU type 19 rod bundle. Nuclear Engineering and Design55 (1979) 389–39410.1016/0029-5493(79)90117-1Suche in Google Scholar

35 Nikuradse, J.: Gesetzmäßigkeiten der turbulenten Strömung in glatten Rohren. VDI Fortschrittshefte356 (1932)10.1007/BF02716946Suche in Google Scholar

36 EiflerW.; Nijsing, R.: VELASCO – velocity field in asymmetric rod configurations. EURATOM, Rep. EUR- 4930e (1973)Suche in Google Scholar

37 Carlucci, L. N.; Hammouda, N.; Rowe, D. S.: Two Phase turbulent mixing and buoyancy drift in rod bundle. Nuclear Engineering and Design227 (2003) 65–8410.1016/j.nucengdes.2003.08.003Suche in Google Scholar

38 Leung, K. H.; Novog, D. R.: Evaluation of ASSERT-PV V3R1 against the PSBT benchmark. Science and Technology of Nuclear Installations2012 (2012), 10.1155/2012/863503Suche in Google Scholar

39 Serizawa, A.; Kataoka, I.: Turbulence suppression in bubbly two-phase flow. Nuclear Engineering and Design122 (1990) 1–1610.1016/0029–5493(90)90193–2Suche in Google Scholar

40 Wheeler, J. E.: Experimental studies on the effects of a spacer grid in a 1 × 3 rod bundle single and two-phase flow. Ms Thesis, 2014, The Pennsylvania State UniversitySuche in Google Scholar

41 Paranjape, S.; Chen, S.; Hibiki, T.; Ishii, M.: Flow regime identification under adiabatic upward two-phase flow in a vertical rod bundle geometry. Journal of Fluids Engineering133 (2011), 10.1115/1.4004836Suche in Google Scholar

42 Green, C.: Experimental study on the effect of spacer grid in two-phase flow through a 1 × 3 rod bundle, 2012, The Pennsylvania State UniversitySuche in Google Scholar

43 Das gupta, A.; Chandraker, D. K.; Vijayan, P. K.; Saha, D.: Steady state subchannelanalysis of AHWR fuel cluster. BARC/2006/E/018 (2006)Suche in Google Scholar

44 Kjellstrom, B.: Studies of turbulent flow parallel to a rod bundle of triangular array. AB Atomenergi, Report AE-RV 196, Sweden (1971)Suche in Google Scholar

45 Trupp, A. C.; Azad, R. S.: The structure of turbulent flow in triangular array rod bundles. Nuclear Engineering and Design32 (1975) 47–8410.1016/0029-5493(75)90090-4Suche in Google Scholar

46 Drain, L. E.: The Laser Doppler Technique. (John Wiley and Sons, New York, 1980) pp. 36–50Suche in Google Scholar

47 Rowe, D. S.; Angel, C. W.: Cross flow mixing between parallel flow channel during boiling, Part III: Effect of spacer on mixing between two channels. BettelleNortwest, BNWL-371, (1969) 10.2172/4823782Suche in Google Scholar