Multi-solid multi-channel Mithrandir (M3) code for thermal–hydraulic modelling of ITER Cable-in-Conduit Superconductors
作者： L. Savoldi Richard , M. Bagnasco , R. Zanino
DOI: 10.1016/J.FUSENGDES.2007.04.035
关键词: Hydraulics 、 Electrical conductor 、 Tokamak 、 Thermal conduction 、 Physics 、 Thermal hydraulics 、 Fusion power 、 Nuclear physics 、 Heat transfer 、 Thermonuclear fusion 、 Mechanics
摘要: We present a new multi-solid multi-channel (M 3 ) thermal–hydraulic model for the analysis of International Thermonuclear Experimental Reactor (ITER) Cable-In-Conduit Conductors (CICC). The discretizes cross section an ITER CICC into M current carrying cable elements (e.g., six last-but-one cabling stages—the petals), coupled with N hydraulic channels petals + central channel) and K non-current solid components jacket CICC), M, arbitrary integers. Along each 1D transient heat conduction equation is solved, whereas along three Euler-like equations, derived from conservation laws compressible He flow, are solved. resulting quasi 3D model, in which equations by mass transfer between different components, implemented code validated against experimental results Good Joint sample Poloidal Field Conductor Insert Full Size Sample. able to reproduce good accuracy
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