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18 Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Fig. 2.1 Overview of thermal-hydraulic challenges in liquid-metal-cooled reactors.

the technology road map for nuclear energy published by the NEA in 2015
l
(IEA/NEA, 2015);
the Task Force on Advanced Reactor Experimental Facilities (TAREF) document for
l
sodium fast reactor safety from the OECD/NEA (OECD/NEA TAREF, 2011);
l the document on CFD codes for nuclear reactor safety issues that partly covers topics related
to liquid-metal-cooled reactors from the OECD/NEA (OECD/NEA CSNI, 2015);
l the 2013 strategic research and innovation agenda from SNE-TP (SNE-TP, 2013);
l the comprehensive report reviewing the Generation IV systems published by the technical
support organization of the French regulator in 2015 (IRSN, 2015).
As a third source of information, open (scientific) literature and conference proceed-
ings are used.
The following publication expresses the international experience:

l Europe: Roelofs (2009), Tenchine (2010), Roelofs et al. (2013), Piala et al. (2014),
Gu enadou et al. (2015), and Roelofs et al. (2015a,b).
l The United States: Todreas (2009) and Sienicki et al. (2003). Especially with respect to high-
fidelity simulations, their work on fast reactors is presented by Merzari et al. (2017).
l India: Chellapandi and Velusamy (2015) and Velusamy et al. (2010).
l Russia: Rogozhkin et al. (2013).
l Japan: Akimoto et al. (2009) and Kamide (2016).
l South Korea: Song et al. (2009).
This process of identification was supplemented by information obtained in dedicated
meetings with European liquid-metal fast reactor designers including input from their
(pre)licensing activities.