Thermofluid-dynamic assessment of the dual cooling scheme EU-DEMO divertor cassette

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
F.M. Castrovinci , A. Quartararo , S. Basile , G. Bongiovì , R. Burlon , P. Chiovaro , P.A. Di Maio , A. Gioè , S. Maggio , G. Mazzone , E. Tomarchio , S. Vacca , E. Vallone , J.-H. You
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引用次数: 0

Abstract

The EU-DEMO divertor is currently foreseen to employ a dual cooling scheme, which involves two separate cooling circuits for the Cassette Body (CB) and the Vertical Targets (VTs), provided with cooling water at distinct operating conditions. Following the EU-DEMO project Gate Review 1, the cassette design has been revised to employ a high-temperature (295-328 °C) and high-pressure (15.5 MPa) coolant for the CB cooling circuit. These design assumptions present novel challenges in achieving uniform and effective cooling of the structure, to ensure reliable operation over the intended lifetime. Furthermore, alternative materials for the VTs-supporting Target Support Bodies (TSBs), namely CuCrZr, SS 316Ti and Eurofer97, are currently being evaluated to extend the operational lifetime of these components under irradiation. The University of Palermo, in collaboration with EUROfusion and ENEA, analysed the steady-state thermal-hydraulic performance of the EU-DEMO divertor cooling circuits with an integrated conjugate heat transfer analysis campaign of the entire divertor cassette, with the twofold aim to evaluate the CB thermal performance under the revised coolant conditions and to compare the temperature distribution in the TSBs with the different materials considered. The work was carried out following a numerical approach based on the finite volume method and adopting the ANSYS CFX computational fluid-dynamic commercial code. Models, loads and boundary conditions are herewith reported and critically discussed, together with the main outcomes obtained.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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