Page 98 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

72 Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Fig. 3.1.10 Reconstructed instantaneous concentration field in a bundle geometry, determined
by LIF. Left: Measured fluorescence intensity; right: reconstructed concentration field.
(Adopted from Wang, X., Wang, R., Du, S., Chen, J., Tan, S., 2016. Flow visualization and
mixing quantification in a rod bundle using laser induced fluorescence. Nucl. Eng. Des. 305,
1–8.)

some complex physical phenomena might be (un)intentionally discarded in CFD sim-
ulations. Therefore, a physical model is needed to provide the required information
and also the necessary validation data for CFD and system codes.
Water modeling (Tenchine, 2010) studies focused on the global thermal-hydraulic
behavior in the upper plenum and lower plenum have been performed for the devel-
opment of sodium fast reactor in France, Japan, Germany, and India (Table 3.1.3).
Thewater modelsCOLCHIX(scale1/8)and JESSICA(scale 1/3) havebeen builtby
CEAtostudytheflowfieldintheabovecoreregionundersteady-stateconditionsandin
transient regimes. Temperature evolution in the above core region was measured at the

Table 3.1.3 List of existing models serving nuclear reactors (Spaccapaniccia, 2016)

Model Scale Reactor Similarity References
COLCHIX 1:8 EFR Ri, 10Pe, relaxed Re Tenchine (2010)
JESSICA 1:3 EFR Relaxed Re Tenchine (2010)
COCO 1:10 EFR Ri, 10Pe, 100 Re Tenchine (2010)
RAMONA 1:20 EFR Ri, Pe, Eu, Hoffman et al. (1985),
relaxed Re Ieda et al. (1985)
NEPTUN 1:5 EFR Ri, Pe, Eu, Hoffman et al. (1985),
relaxed Re Ieda et al. (1985)
SAMRAT 1:4 PFBR Ri, 10Pe, 100 Re Padmakumar et al.
(2013)
AQUARIUM 1:10 JSFR Ri, relaxed Pe, Ushijima et al. (1991)
relaxed Re