Margherita Sardo , Samuli Heikkinen , Jose Pacheco , Emir Örer , Taner Hergül , Can Uzel Osman , Hayao Eguchi , Masato Arai , Marta Freitas , Nuno A. Marques , Sergio A. Reis , Mónica Mendes Reis
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引用次数: 0
Abstract
Precipitation hardened CuCrZr is one of the materials for the ITER First Wall Panel (FWP) application. It is used as an intermediate layer between the stainless-steel structure and the W armour facing the plasma, with embedded water-cooling channels. Because of its high thermal conductivity combined with high strength this alloy is used as the FWP heatsink. Within the European Normal Heat Flux FWP, the three layers are joined by the Hot Isostatic Pressing (HIP) diffusion bonding process.
Past studies defined the optimum parameters for the CuCrZr material, considering the loads present on the ITER machine such as high thermo-mechanical stresses and fast neutron damage. Attention is given to material testing for mechanical properties at room and elevated temperature and microstructure to ensure compliant material of the EU FWP.
The comparison between real HIP sequence and HIP simulation on the resulting material properties demonstrates suitability of the approach.
The CuCrZr material produced has been used for the qualification of the HIP processes of the EU FWP, which increases the confidence on a successful FWP series production. This paper summarizes the EU FWP CuCrZr material’s mechanical and microstructural test results, obtained by the ISQ laboratory, showing compliance with ITER material requirements and a high consistency and coherence on the material properties along the production and among different material suppliers. Also, it provides an overview of the material quantities procured over the past years and the future needs for the EU FWP production.
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.