References
- U. Rohdea, T. Hohnea, S. Kliema, B. Hemstromb, M. Scheuererc, T. Toppilad, A. Aszodie, I. Borose, I. Farkasf, P. Muhlbauerg, L. Vyskocilg, J. Klepach, J. Remish, T. Dury, Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor-validation of CFD codes, Nucl. Eng. Des. 237 (2007) 1639-1655. https://doi.org/10.1016/j.nucengdes.2007.03.015
- H.D. Kweon, J.S. Kim, K.Y. Lee, Fatigue design of nuclear class piping considering thermal stratification, Nucl. Eng. Des. 238 (2008) 1265-1274. https://doi.org/10.1016/j.nucengdes.2007.11.009
- E.C. Eggertson, R. Kapulla, J. Fokken, H.M. Prasser, Turbulent mixingand its effectsonthermal fatigue innuclear reactors, Int. J. Math. Comput. Phys. Electr. Comput. Eng. 52 (2011) 206-213.
- K.J. Metzner, U. Wilke, Thermal Fatigue Evaluation of Piping System Tee-Connections (THERFAT) [Internet]. 2007 [cited 2016 Mar 23]. Available from: http://cordis.europa.eu/documents/documentlibrary/97848051EN6.pdf.
- S.,M. Hosseini, K. Yuki, H. Hashizume, Classification of turbulent jets in a T-junction area with a 90-deg bend upstream, Int. J. Heat Mass Transf. 51 (2007) 2444-2454.
- International Atomic Energy Agency (IAEA), Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment, Deterministic Evaluation for the Integrity of Reactor Pressure Vessel (Rep. No. IAEA-TECDOC-1627), IAEA, Vienna, Austria, 2010.
- C. Stephan, High cycle thermal fatigue damage prediction in mixing zones of nuclear power plants: engineering issues illustrated onthe FATHER case, Procedia. Eng. 66 (2013) 240-249. https://doi.org/10.1016/j.proeng.2013.12.079
- K.E. Stahlkopf, Pressure vessel integrity under pressurized thermal shock conditions, Nucl. Eng. Des. 80 (1984) 171-180. https://doi.org/10.1016/0029-5493(84)90165-1
- S.M. Hosseini, K. Yuki, H. Hashizume, The three-dimensional study of flow mixing phenomenon in a T-junction area with 90-degree bend upstream, Proceedings of the International Conference "Nuclear Energy for New Europe 2005," Bled (Slovenia), September 5-8, 2005. 037.1-037.10.
- C. Faidy, Thermal fatigue in mixing areas: status and justification of French assessment method, Proceedings of the Third International Conference on Fatigue of Reactor Components, EPRI/US NRC/OECD NEA, Seville, Spain, 2004.
- T. Muramatsu, Numerical analysis of non-stationary thermal response characteristics for a fluid-structure interaction system, J. Press. Vessel Technol. 121 (1999) 276-282. https://doi.org/10.1115/1.2883703
- H. Ezddin, G. Valer, F. Istvanne, E. Gyorgy, B. Gabor, Investigation of mixing coolant in a model of reactor vessel down-comer and in cold leg inlets using PIV, LIF, and CFD techniques, Therm. Sci. (2015) 121-134.
- M. Igarashi, Study on fluid mixing phenomena for evaluation of thermal striping a mixing tee, 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulic (NURETH-10), Seoul, Korea, 2003, pp. 1-12.
- M. Tanaka, Experimental investigation of flow field structure in mixing tee, Proceedings of Sixth International Conference on Nuclear Thermal Hydraulics, Operation and Safety, (NUTHOS-6), Nara, Japan, 2004.
- S.M. Hosseini, Experimental investigation of thermalhydraulic characteristics at a mixing tee, International Heat Transfer Conference (FCV-17), Sydney, Australia, 2006.
- N. Kimura, M. Nishimura, H. Kamide, Study on convective mixing for thermal striping phenomena: experimental analyses on mixing process in parallel triple-jet and comparisons between numerical methods, JSME Int. J. 45 (2002) 592-599. https://doi.org/10.1299/jsmeb.45.592
- H. Ogawa, M. Igarashi, N. Kimura, H. Kamide, Experimental study on fluid mixing phenomena in T-pipe junction with upstream elbow, 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Popes Palace Conference Center, Avignon, France, 2005.
- N. Aminia, Y.A. Hassan, Measurements of jet flows impinging into a channel containing rod bundle using dynamic PIV, Int. J. Heat Mass Transf. 52 (2009) 5479-5495. https://doi.org/10.1016/j.ijheatmasstransfer.2009.07.002
- Fluent, Inc, FlowLab 1.2, Turbulent Flow and Heat Transfer in a Mixing Elbow, 2007. Available from: https://www.yumpu.com/en/document/view/3338571/turbulent-flow-and-heattransfer-in- a-mixing-elbow/6.
- V. Gottlasz, E. Hutli, D. Tar, G. Ezsol, G. Baranyai, Measuring of velocity and temperature field in a model of reactor vessel, downcomer and cold-legs inlets, 10th International Symposium on Particle Image Velocimetry-PIV13, Delft, the Netherlands, July 2-4, 2013, pp. 1-9.
- H. Ezddin, G. Valer, T. Daniel, E. Gyorgy, B. Gabor, Experimental approach to investigate the dynamics of mixing coolant flow in complex geometry using PIV and PLIF techniques, Therm. Sci. 19 (2015) 989-1004. https://doi.org/10.2298/TSCI130603051H
- T. Hohne, S. Kliem, U. Rohde, F.-P. Weiss, Boron dilution transients during natural circulation flow in PWR-experiments and CFD simulations, Nucl. Eng. Des. 238 (2008) 1987-1995. https://doi.org/10.1016/j.nucengdes.2007.10.032
- T. Hohne, S. Kliem, Modeling of a buoyancy-driven flow experiment in pressurized water reactors using CFDmethods, Nucl. Eng. Technol. 39 (2007) 327-336. https://doi.org/10.5516/NET.2007.39.4.327
- T. Hohne, Numerical simulation of coolant mixing in a pressurized water reactor with different CFD methods based on complex meshes, Int. J. Nucl. Energy Sci. Technol. 3 (2013) 399-412.
- S. Kliem, T. Hohne, U. Rohde, F.-P. Weiss, Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high-resolution measurement techniques and numerical modeling, Nucl. Eng. Des. 240 (2010) 2271-2280. https://doi.org/10.1016/j.nucengdes.2009.11.015
- V. Petrov, A. Manera, Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPRTM: CFD investigations and comparison with experimental results, Nucl. Eng. Des. 241 (2011) 1478-1485. https://doi.org/10.1016/j.nucengdes.2011.02.027
- G. Pochet, X. Zhang, D. Leonard, CFD simulations of buoyancy driven flow mixing experiments performed at the ROCOM facility, Presented at the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14), Toronto, Canada, September 25-30, 2011.
- V. Petrov, A. Manera, Validation of Star-CCM+ for buoyancy driven mixing in a PWR reactor pressure vessel, Presented at the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14), Toronto, Canada, September 25-30, 2011.
- S. Kliem, H.-M. Prasser, T. Suhnel, F.-P. Weiss, A. Hansen, Experimental determination of the boron concentration distribution in the primary circuit of a PWR after a postulated cold leg small break loss-of-coolant:accident with cold leg safety injection, Nucl. Eng. Des. 238 (2008) 1788-1801. https://doi.org/10.1016/j.nucengdes.2007.10.016
- H.-M. Prasser, G. Grunwald, Th. Hohne, S. Kliem, U. Rohde, F.-P. WeiB, Coolant mixing in a PWR-de-boration transients, steam line breaks and emergency core cooling injection-experiments and analyses, Nucl. Technol. 143 (2003) 37-56. https://doi.org/10.13182/NT03-A3396
- M.J. da Silva, S. Thiele, T. Hohne, R. Vaibar, U. Hampel, Experimental studies and CFD calculations for buoyancy driven mixing phenomena, Nucl. Eng. Des. 240 (2010) 2185-2193. https://doi.org/10.1016/j.nucengdes.2009.11.023
- A. Bucalossi, F. Moretti, D. Melideo, A. Del Nevo, F. D'Auria, T. Hohne, E. Lisenkov, D. Gallori, Experimental investigation of in-vessel mixing phenomena in a VVER-1000 scaled test facility during unsteady asymmetric transients, Nucl. Eng. Des. 241 (2011) 3068-3075. https://doi.org/10.1016/j.nucengdes.2011.05.005
- S.T. Jayaraju, P. Sathiah, E.M.J. Komen, E. Baglietto, Large Eddy simulation for an inherent boron dilution transient, Nucl. Eng. Des. 262 (2013) 484-498. https://doi.org/10.1016/j.nucengdes.2013.05.024
- J.H. Mahaffy, B. Chung, F. Dubois, F. Ducros, E. Graffard, M. Heitsch, M. Henriksson, E. Komen, F. Moretti, T. Morii, P. Muhlbauer, U. Rohde, M. Scheuerer, B.L. Smith, C. Song, T. Watanabe, G. Zigh, Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety, Nuclear Energy Agency, Paris, France, 2007 (Rep. No. NEA/CSNI/R5).
- H.-M. Prasser, A. Bottger, J. Zschau, A new electrode-mesh tomograph for gaseliquid flows, Flow Meas. Instrum. 9 (1998) 111-119. https://doi.org/10.1016/S0955-5986(98)00015-6
- S. Kliem, Comparison of the results of the pre-test calculations with the experimental data for ROCOM tests 1.1 and 1.2, 1st PKL2 Analytical Workshop, Pisa, Italy, 2010.
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