Abstract
The thermal-hydraulics challenges of a nuclear reactor are numerous and their investigation is crucial for the
design and safety of new reactors. Numerical simulation through CFD codes or System thermal hydraulics codes
can address a lot of the different challenges; nevertheless the use of water modeling for the study and validation
of the thermal hydraulic behavior of a new primary system remains a valuable tool. A water model of the pooltype
liquid metal-cooled MYRRHA reactor has been developed at the von Karman Institute in collaboration with
SCK•CEN. It is a full Plexiglas model at a geometrical scale 1/5 of the design version 1.2 of MYRRHA. The scaling
was performed by respecting as much as possible the Richardson, Euler, Reynolds and Péclet numbers’ similarity
with MYRRHA. This transparent water model allows the application of optical measurement techniques for the
flow characterization. Different transient tests relevant for MYRRHA have been defined by SCK•CEN. These test
cases have been studied using the water model facility. They include the study of the transient thermal hydraulic
behavior when switching from forced to Loss-of-Flow (LOF), the failure of a single pump, the failure of one of the
four heat exchangers and the loss of coolant inventory (LOC). Results of phenomenological behavior are presented
as well as the time–dependent variation of temperatures recorded with different arrays of thermocouples
immersed inside the upper plenum.
Original language | English |
---|---|
Pages (from-to) | 10-16 |
Number of pages | 7 |
Journal | Nuclear Engineering and Design |
Volume | 346 |
DOIs | |
State | Published - 18 Feb 2019 |