CFD modelling of supercritical water flow and heat transfer in a 2 × 2 fuel rod bundle

Ambrosini, 2009, Continuing assessment of system and CFD codes for heat transfer and stability in supercritical fluids Angelucci, 2013, Numerical estimation of wall friction ratio near the pseudo-critical point with CFD-models, Nucl. Eng. Des., 264, 71, 10.1016/j.nucengdes.2013.02.022 Bergmann, 2015, Sensitivity studies of SST turbulence model parameters on the prediction of 7-rod bundle benchmark experiments, J. Nucl. Eng. Radiat. Sci., 2, 10.1115/1.4031035 Chang, 2015, Numerical study of supercritical heat transfer in a seven-rod bundle Cheng, 2001 Cho, 2009, Prediction of a heat transfer to CO2 flowing in an upward path at a supercritical pressure, Nucl. Eng. Technol., 41, 907, 10.5516/NET.2009.41.7.907 Durbin, 1995, Separated flow computations with the k–ɛ–v2 model, AIAA J., 33, 659, 10.2514/3.12628 GIF Annual Report, 2014 Hamman, 2008, A CFD M&S process for fast reactor fuel assemblies He, 2008, Assessment of performance of turbulence models in predicting supercritical pressure heat transfer in a vertical tube, Int. J. Heat Mass Transf., 51, 4659, 10.1016/j.ijheatmasstransfer.2007.12.028 Kao, 2010, Heat transfer deterioration in a supercritical water channel, Nucl. Eng. Des., 240, 3321, 10.1016/j.nucengdes.2010.06.028 Kays, 1994, Turbulent Prandtl number – where are we?, J. Heat Transf., 116, 284, 10.1115/1.2911398 Laurien, 2010, Numerical simulation of flow and heat transfer of fluids at super critical pressure Lemmon, 2015, Thermophysical properties of fluid systems Leung, 2016, Assessment of the computational tools in support of heat transfer correlation development for the fuel assembly of Canadian supercritical water cooled reactor, ASME J. Nucl. Eng. Radiat. Sci., 2 Liu, 2013, Heat transfer deterioration to supercritical water in circular tube and annular channel, Nucl. Eng. Des., 255, 97, 10.1016/j.nucengdes.2012.09.025 Menter, 1994, Two-equation eddy-viscosity turbulence modeling for engineering applications, AIAA J., 32, 1598, 10.2514/3.12149 Nemati, 2013, Direct numerical simulation of turbulent flow with supercritical fluid in a heated pipe Palko, 2008, Theoretical and numerical study of heat transfer deterioration in high performance light water reactor, Sci. Technol. Nucl. Install., 1–5 Peng, 1999, Computation of turbulent buoyant flows in enclosures with low-Reynolds-number k–ω models, Int. J. Heat Fluid Flow, 20, 172, 10.1016/S0142-727X(98)10050-4 Pioro, 2007 Podila, 2014, Assessment of CFD for the Canadian SCWR bundle with wire wraps, Prog. Nucl. Energy, 77, 373, 10.1016/j.pnucene.2014.02.009 Rohde, 2015, A blind, numerical benchmark study on supercritical water heat transfer experiments in a 7-rod bundle Ruzickova, 2014, Overview and progress in the European Project: “supercritical water reactor-fuel qualification test”, Prog. Nucl. Energy, 77, 381, 10.1016/j.pnucene.2014.01.011 Schulenberg, 2013, Thermal-hydraulics and safety concepts of supercritical water cooled reactors, Nucl. Eng. Des., 264, 231, 10.1016/j.nucengdes.2012.08.040 Shams, 2015, High-fidelity numerical simulation of the flow through an infinite wire-wrapped fuel assembly Shams, 2011, Influence of numerical tools on the flow and heat transfer of supercritical water STAR-CCM+, 2015. website: http://www.cd-adapco.com/products/STAR-CCM plus/. Sosnovsky, 2015, CFD simulations to determine the effects of deformations on liquid metal cooled wire wrapped fuel assemblies Wang, 2014, Experimental investigation of heat transfer from a 2×2 rod bundle to supercritical pressure water, Nucl. Eng. Des., 275, 205, 10.1016/j.nucengdes.2014.04.036 Wigeland, 2009, Fast reactor subassembly design modifications for increasing electricity generation efficiency Xiong, 2015, Numerical analysis on supercritical water heat transfer in a 2×2 rod bundle, Ann. Nucl. Energy, 80, 123, 10.1016/j.anucene.2015.02.005 Zhang, 2012, Experimental and numerical investigation of turbulent convective heat transfer deterioration of supercritical water in vertical tube, Nucl. Eng. Des., 248, 226, 10.1016/j.nucengdes.2012.03.026 Zhou, 2014