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Thermal-hydraulic challenges                                   2


           in liquid-metal-cooled reactors

                                   †
                                                ‡
           F. Roelofs*, A. Gerschenfeld , M. Tarantino ,
                        §
           K. Van Tichelen , W. D. Pointer ¶
                                                                    †
           *Nuclear Research & Consultancy Group (NRG), Petten, The Netherlands, CEA, Gif-sur-
                                                                      ¶
                                                  §
                       ‡
           Yvette, France, ENEA, Kista, Stockholm, Sweden, SCK CEN, Mol, Belgium, Oak Ridge
                                                      l
           National Laboratory, Oak Ridge, TN, United States
           2.1   Introduction

           This chapter provides an overview of the thermal-hydraulic challenges that can pre-
           sent themselves in liquid-metal-cooled reactors with a focus on pool-type reactors.
              In the first two sections, the important process of identification of the challenges is
           briefly described, as well as their separation in different categories. As a preview, the
           challenges identified are summarized in Fig. 2.1 where they have been subdivided in
           basic, core, pool, and system thermal-hydraulic phenomena. All challenges are briefly
           described and explained in the subsequent sections.


           2.2   Identification

           To identify if the thermal-hydraulic challenge designers and safety analysts are con-
           fronted with when developing a liquid-metal-cooled reactor, multiple sources have
           been consulted.
              A first source of information can be found in the various collaborative European
           research projects that are performed in the framework programs sponsored by Euro-
           pean Commission dealing with SFR and LFR development. Important projects to
           be mentioned here are ADRIANA, ASCHLIM, CDT, EISOFAR, ESFR, ELSY,
           ESFR-SMART, ESNII+, EUROTRANS, HeLiMnet, LEADER, MAXSIMA,
           MYRTE, SEARCH, SESAME, THINS, and VELLA. More information about these
           projects can be obtained at the website of the European Commission: http://cordis.
           europa.eu/.
              A second source consists of information collected by international organizations
           and initiatives, such as
              the technology road map (GIF, 2002) and it’s update (GIF, 2014) from the Generation IV
           l
              International Forum;
           l  the 1999 and 2012 status updates of fast reactor research and technology from the IAEA
              (IAEA, 1999, 2012);
           l  the summary report of the recent IAEA workshop on priorities in modeling and simulation
              for fast neutron systems (IAEA, 2014);

           Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors. https://doi.org/10.1016/B978-0-08-101980-1.00002-8
           Copyright © 2019 Elsevier Ltd. All rights reserved.
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