Page 376 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
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           Prakash, V., Thirumalai, M., Anandaraj, M., Anup Kumar, P., Ramdasu, D., Pandey, G.,
               Padmakumar, G., Anandbabu, C., Kalyanasundaram, P., 2011. Experimental qualifica-
               tion of subassembly design for prototype fast breeder reactor. Nucl. Eng. Des. 241,
               3325–3332.
           Ranjan, R., Pantano, C., Fischer, P., 2010. Direct simulation of turbulent swept flow over a wire
               in a channel. J. Fluid Mech. 651, 165–209.
           Roelofs, F., Gopala, V., Chandra, L., Viellieber, M., Class, A., 2012. Simulating fuel assemblies
               with low resolution CFD approaches. Nucl. Eng. Des. 250, 548–559.
           Roelofs, F., Gopala, V.R., Jayaraju, S., Shams, A., Komen, E.M.J., 2013. Review of fuel assem-
               bly and pool thermal hydraulics for fast reactors. Nucl. Eng. Des. 265, 1205–1222.
           Roidt, R., Carelli, M., Markley, R., 1980. Experimental investigations of the hydraulic field in
               wire-wrapped LMFBR core assemblies. Nucl. Eng. Des. 62, 295–321.
           Rolfo, S., Peniguel, C., Guillaud, M., Laurence, D., 2012. Thermal-hydraulic study of a wire
               spacer fuel assembly. Nucl. Eng. Des. 243, 251–262.
           Sato, H., Kobayashi, J., Miyakoshi, H., Kamide, H., 2009. Study on velocity field in a wire
               wrapped fuel pin bundle of sodium cooled reactor – detailed velocity distribution in a sub-
               channel. In: NURETH13, Kanazawa, Japan.
           Schultheiss, G.F., 1987. On local blockage formation in sodium cooled reactors. Nucl. Eng. Des.
               100, 427–433.
           Shams, A., Roelofs, F., Komen, E., 2015. High-fidelity numerical simulation of the flow
               through an infinite wire-wrapped fuel assembly. In: NURETH16, Chicago, USA.
           Shams, A., Roelofs, F., Baglietto, E., Komen, E., 2018. High fidelity numerical simulations of
               an infinite wire-wrapped fuel assembly. Nucl. Eng. Des. 335, 441–459.
           Sosnovsky, E., Baglietto, E., Keijers, S., Van Tichelen, K., Cardoso de Souza, T., Doolaard, H.,
               Roelofs, F., 2015. CFD simulations to determine the effects of deformations on liquid
               metal cooled wire wrapped fuel assemblies. In: NURETH16, Chicago, USA,
               pp. 2747–2761.
           Tenchine, D., 2010. Some thermal hydraulic challenges in sodium cooled fast reactors. Nucl.
               Eng. Des. 240, 1195–1217.
           Ter Hofstede, E., Kottapalli, S., Shams, A., 2016. Numerical prediction of flow induced vibra-
               tions for safety in nuclear reactor applications. In: CFD4NRS6, Boston, USA.
           Uwaba, T., Ohshima, H., Ito, M., 2017. Analyses of deformation and thermal-hydraulics within
               a wire-wrapped fuel assembly in a liquid metal fast reactor by the coupled code system.
               Nucl. Eng. Des. 317, 133–145.
           Vaghetto, R., Goth, N., Childs, M., Jones, P., Lee, S., Nguyen, D.T., Hassan, Y.A., 2016.
               Flow field and pressure measurements in a 61-pin wire-wrapped bundle. ANS 115. Las
               Vegas, USA.
           Viellieber, M., 2017. Coarse-Grid-CFD f€ ur industrielle Anwendungen: Integrale Analysen
               detaillierter generischer Simulationen zur Schließung von Feinstrukturtermen eines
               Multiskalenansatzes. PhD Thesis, KIT Scientific Reports 7727, Karlsruhe, Germany
               (in German).
           Viellieber, M., Class, A., 2012. Anisotropic porosity coarse-grid CFD for computationally
               intensive applications with repetitive flow patterns. In: ENC2012, Manchester, UK.
           Viellieber, M., Class, A., 2014. Sub channel scale resolution in homogenization codes by the
               coarse-grid-CFD. In: THINS 2014 International Workshop, Modena, Italy.
           Viellieber, M., Class, A., 2015. Investigating reactor components with the coarse grid method-
               ology. In: NURETH16, Chicago, USA.
           Wantland, J., Gnadt, P., MacPherson, R., Fontana, M., Hanus, N., Smith, C., 1976. The effects
               of duct configuration on flow and temperature structure in sodium-cooled 19-rod simulated
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