Measurements Methods for the analysis of Nuclear Reactors Thermal Hydraulic in Water Scaled Facilities

von Karman Institute of Fluid Dynamics Belgium

^* Von Karman Institute for Fluid Dynamics, Rhode Saint Genese, 1640, Belgium Email: chiara.spaccapaniccia@vki.ac.be
^* Von Karman Institute for Fluid Dynamics, Rhode Saint Genese, 1640, Belgium Email: philippe.planquart@vki.ac.be
^* Von Karman Institute for Fluid Dynamics, Rhode Saint Genese, 1640, Belgium Email: buchlin@vki.ac.be

Published online: 10 January 2018

Abstract

The Belgian nuclear research institute (SCK•CEN) is developing MYRRHA. MYRRHA is a flexible fast spectrum research reactor, conceived as an accelerator driven system (ADS). The configuration of the primary loop is pool-type: the primary coolant and all the primary system components (core and heat exchangers) are contained within the reactor vessel, while the secondary fluid is circulating in the heat exchangers. The primary coolant is Lead Bismuth Eutectic (LBE). The recent nuclear accident of Fukushima in 2011 changed the requirements for the design of new reactors, which should include the possibility to remove the residual decay heat through passive primary and secondary systems, i.e. natural convection (NC). After the reactor shut down, in the unlucky event of propeller failures, the primary and secondary loops should be able to remove the decay heat in passive way (Natural Convection). The present study analyses the flow and the temperature distribution in the upper plenum by applying laser imaging techniques in a laboratory scaled water model. A parametric study is proposed to study stratification mitigation strategies by varying the geometry of the buffer tank simulating the upper plenum.