CFD analysis of the ITER first wall 06 panel. Part II: Thermal-hydraulics |
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| Affiliation: | 1. Dipartimento Energia, Politecnico di Torino, 10129 Torino, Italy;2. Fusion for Energy, 08019 Barcelona, Spain;1. JT-60SA EU Home Team, Fusion for Energy, Boltzmannstrasse 2, Garching 85748, Germany;2. JT-60SA JA Home Team, Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193, Japan;3. JT-60SA JA Project Team, Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193, Japan;1. Shanghai Key Laboratory of Special Artificial Microstructure Materials and Technology, School of Physics Science and Engineering, Tongji University, Shanghai 200092, China;2. Shanghai Institute of Laser Plasma, Shanghai 201800, China |
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| Abstract: | The computational fluid dynamics (CFD) analysis of the FW06 panel of the ITER shielding blanket is presented in two companion papers. In this Part II we concentrate on the thermal-hydraulics of the water coolant, driven by the nuclear volumetric and plasma surface heat loads discussed in Part I. Both the detailed steady state analysis of a single cooling channel and the coarse transient analysis of the whole panel are considered. The compatibility of the hot spots with the maximum recommended temperatures for the different materials is confirmed. The heat transfer coefficient between coolant and walls is obtained post-processing the results of the simulation and compared with the results of available correlations, which may be used for simpler analyses: in the fully developed flow regions of the cooling pipes, it turns out to be well approximated by the Sieder–Tate correlation. The operation margin with respect to the critical heat flux is also computed and turns out to be sufficiently large compared with the design limit. |
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| Keywords: | Nuclear fusion ITER First wall Thermal-hydraulics CFD |
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