I. Pagani , F. Lucca , G. Mariani , S. Iglesias , F. Penzel
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引用次数: 0
Abstract
The ITER First Wall Samples Diagnostic is designed to measure the erosion and fuel retention on the First Wall (FW), caused by the load of the Charge Exchange Neutral (CXN) particles.
Ensuring the structural integrity of the FW under extreme conditions is vital for the ITER Tokamak's performance, particularly during Major Disruptions (MD) and Vertical Disruption Events (VDE), which generate intense mechanical and electromagnetic stresses. To address these challenges, a comprehensive electromagnetic (EM) analysis was conducted using advanced Finite Element (FE) modeling techniques.
A key aspect of this study was the application of a sub-modelling technique that enabled precise calculation of EM loads on individual FWS components. By focusing on specific regions of interest, the sub-modelling approach provided more detailed insights into the forces and moments generated by Lorentz forces and the impact of halo currents during plasma disruptions. This method transferred electromagnetic data from a global model to localized sub-models, ensuring accurate load predictions while reducing computational complexity.
The results demonstrate that the sub-modelling approach accurately predicts the total forces and moments acting on the FW samples, particularly identifying radial forces and torques as the dominant stress factors. The analysis revealed that the sample adapter component experiences over 90 % of the total load. These findings are instrumental in guiding the design and improving the reliability of FWS diagnostics, ensuring their functionality and durability under ITER's extreme operating conditions.
This study highlights the effectiveness of integrating global and sub-modelling techniques for assessing complex loading scenarios, contributing to the optimization of ITER's diagnostic components.
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.