Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
Online ISSN : 2424-2934
セッションID: ICONE15-10493
会議情報
ICONE15-10493 PRE DESIGN OF A MOLTEN SALT THORIUM REACTOR LOOP
Jean-Pierre CaireAnthony Roure
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会議録・要旨集 フリー

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This study is a contribution to the 2004 PCR-RSF program of the Centre National de la Recherche Scientifique (CNRS) devoted to research on high temperature thorium molten salt reactors. A major issue of high temperature molten salt reactors is the very large heat duty to be transferred from primary to secondary loop of the reactor with minimal thermal losses. A possible inner loop made of a series of conventional graphite filter plate exchangers, pipes and pumps was investigated. The loop was assumed to use two counter current flows of the same LiF, BeF_2, ZrF_4, UF_4 molten salt flowing through the reactor. The 3D model used the coupling of k-ε turbulent Navier-Stokes equations and thermal applications of the Heat Transfer module of COMSOL Multiphysics. For a reactor delivering 2700 MWth, the model required a set of 114 identical exchangers. Each one was optimized to limit the heat losses to 2882 W. The pipes made of a succession of graphite, ceramics, Hastelloy-N alloy and insulating Microtherm^[○!R] layers led to a thermal loss limited to 550 W per linear meter. In such conditions, the global thermal losses represent only 0.013 % of the reactor thermal power for elements covered with an insulator only 3 cm thick.
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© 2007 一般社団法人 日本機械学会
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