Application of virtual fitting in the manufacturing of the ITER European vacuum vessel sectors

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Alessandro Lo Bue , Edoardo Pompa , Miguel Gonzalez Fernandez , Francesca Giovanna Lanzotti , Gabriele D'Amico , Boris Bellesia
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引用次数: 0

Abstract

The Vacuum Vessel is one of the main systems of the ITER tokamak. The welded steel, torus-shaped vessel, houses the plasma and acts as a first safety containment barrier. It provides support for In-Vessel components and removes the heat generated during operation by mean of cooling water circulating through its walls. To ensure the functionality of the system, strict geometrical requirements have been defined on several features. The large scale of the component and the complexity of the manufacturing raised the need to develop metrology strategies that improve the awareness of the decision-making processes and minimize the risk of non-compliance of the final product. Virtual Fitting is a technique that enables to find the optimal way of assembling parts together considering their real shapes. By defining requirements to include in the analysis and their priority, an optimum can be found by least square minimization of the as-built data deviation from the nominal reference. The method has been deployed in one of the most critical stages of the Vacuum Vessel production, the assembly of the four poloidal segments composing the final sector. The analysis provided the actors involved several alignment scenarios, from which corrective actions have been derived, in terms of time, cost and quality. Firstly, this paper presents the principles of the Virtual Fitting technique, then the second part focuses on the application of the Vacuum Vessel European Sector #5.
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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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