Page 377 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

340 Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

LMFBR fuel bundles with helical wire-wrap spacers. In: 16th National Heat Transfer
Conference, St. Louis, USA.
Yu, Y., Merzari, E., Obabko, A., Thomas, J., 2015. A porous medium model for predicting the
duct wall temperature of sodium fast reactor fuel assembly. Nucl. Eng. Des. 295, 48–58.
Zhao, P., Liu, J., Ge, Z., Wang, X., Cheng, X., 2017. CFD analysis of transverse flow in a wire-
wrapped hexagonal seven-pin bundle. Nucl. Eng. Des. 317, 146–157.

Further reading

Pacio, J., Wetzel, T., Doolaard, H., Roelofs, F., Van Tichelen, K., 2015. Thermal-hydraulic
study of the LBE-cooled fuel assembly in the MYRRHA reactor: experiments and simu-
lations. In: NURETH16, Chicago, USA, pp. 47–60.