Page 67 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

42 Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Roelofs, F., Shams, A., Pacio, J., Moreau, V., Planquart, P., Van Tichelen, K., Di Piazza, I.,
Tarantino, M., 2015b. European outlook for LMFR thermal hydraulics. In: NURETH16,
Chicago, USApp. 7414–7425.
Roelofs, F., Shams, A., Moreau, V., Di Piazza, I., Gerschenfeld, A., Planquart, P., Tarantino, M.,
2016. Liquid metal thermal hydraulics, state of the art and beyond: the SESAME project.
In: ENC 2016, Warsaw, Poland.
Rogozhkin, S.A., Osipov, S.L., Shepelev, S.F., Aksenov, A.A., Sazonova, M.L., Shmelev, V.V.,
2013. Verification calculations as per CFD FLOWVISION code for sodium-cooled reactor
plants. In: FR13, Paris, France.
Rouault, J., et al., 2015. Japan-France collaboration on the ASTRID program and sodium fast
reactor. In: ICAPP 2015, Nice, France.
Shams, A., 2017. Assessment and calibration of an algebraic turbulent heat flux model for high
Rayleigh number flow regimes. In: ERMSAR-2017, Warsaw, Poland.
Shams, A., Roelofs, F., Baglietto, E., Lardeau, S., Kenjeres, S., 2014. Assessment and calibra-
tion of an algebraic turbulent heat flux model for low-Prandtl fluids. Int. J. Heat Mass
Transfer 79, 589–601.
Sienicki, J., Wade, D., Tzanos, C., 2003. Thermal-hydraulic research and development needs
for lead fast reactors. In: IAEA Tecdoc 1520, Theoretical and Experimental Studies of
Heavy Liquid Metal Thermal-Hydraulics, Karlsruhe, Germany.
SNE-TP, 2013. Strategic Research and Innovation Agenda. ISBN 978-2-919313-04-4.
Song, C.H., Kim, K.K., Hahn, D.H., Lee, W.J., Bae, Y.Y., Hong, B.G., 2009. Thermal-hydraulic
R&Ds for Gen-III+ and Gen-IV reactors at KAERI: issues and future directions.
In: NURETH13, Kanazawa, Japan.
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, USApp. 2747–2761.
Tarantino, M., 2017. International Collaboration on Gen-IV Nuclear Systems: Progress Activ-
ity. CSEA, Rome, Italy.
Tarantino, M., Martelli, D., Barone, G., Di Piazza, I., Forgione, N., 2015. Mixed convection and
stratification phenomena in a heavy liquid metal pool. Nucl. Eng. Des. 286, 261–277.
Tenchine, D., 2010. Some thermal hydraulic challenges in sodium cooled fast reactors. Nucl.
Eng. Des. 240, 1195–1217.
Tenchine, D., Barthel, V., Bieder, U., Ducros, F., Fauchet, G., Fournier, C., Mathieu, B.,
Perdu, F., Quemere, P., Vandroux, S., 2012. Status of TRIO_U code for sodium cooled
fast reactors. Nucl. Eng. Des. 242, 307–315.
Tenchine, D., Fournier, C., Dolias, Y., 2014. Gas entrainment issues in sodium cooled fast reac-
tors. Nucl. Eng. Des. 270, 302–311.
Todreas, N., 2009. Thermal-hydraulic challenges in fast reactor design. Nucl. Technol.
167, 127–144.
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.
Van Tichelen, K., 2012. Blockages in LMFR fuel assemblies. In: FP7 MAXSIMA, SCK.CEN-
R-5433, Mol, Belgium.
Van Tichelen, K., Mirelli, F., 2017. Experimental investigation of steady-state flow in the LBE-
cooled scaled pool facility E-scape. In: NURETH17, Xi’an, China.
Velusamy, K., Chellapandi, P., Chetal, S., Raj, B., 2010. Overview of pool hydraulic design of
Indian prototype fast breeder reactor. Sadhana 35, 97–128.
Vogt, T., Boden, S., Andruszkiewicz, A., Eckert, K., Eckert, S., Gerbeth, G., 2015. Detection of
gas entrainment into liquid metals. Nucl. Eng. Des. 294, 16–23.