As-built based method for virtual alignment and assembly of the ITER tokamak

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Francesca Giovanna Lanzotti , Edoardo Pompa , Gianluca Picci , Alessandro Lo Bue , Giuseppe Di Gironimo , Domenico Marzullo , Gabriele D’Amico
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Abstract

In the project development of large fusion machines, the alignment and assembly phases represent an open challenge. Each mechanical component that constitutes the whole machine assembly and fixtures is affected by an intrinsic geometrical variation due to manufacturing and assembly processes. The complexity of the assembly together with the unavoidable geometrical imperfection can affect the expected machine functionalities. In this context, Reverse Engineering activities, aiming at obtaining the as-built of the components, coupled with virtual fitting studies, defining optimum alignment using the real shape of the components, become powerful risk mitigation tools in the assembly phases. This work presents a systematic method, complementary to the methodology currently followed in the ITER project, for the as-built management and for the validation of alignment phases of such a complex assembly. The first phase is to identify the key assembly requirements which drive the alignment of the ITER assembly. Then, the database for the requirement collection is clearly organized following the proper nomenclature rules and its architecture for data collection and analysis is indeed set up. Four virtual fitting pilot studies are presented to show how the methodology is helpful to assess the assembly requirements in a defined alignment scenario.
基于已建的ITER托卡马克虚拟对准与装配方法
在大型核聚变机的项目开发中,对准和装配阶段是一个公开的挑战。由于制造和装配过程,构成整个机器装配和夹具的每个机械部件都受到固有几何变化的影响。装配的复杂性以及不可避免的几何缺陷会影响预期的机器功能。在这种情况下,旨在获得组件的成品的逆向工程活动,加上虚拟拟合研究,使用组件的真实形状定义最佳对齐,成为装配阶段强大的风险缓解工具。这项工作提出了一种系统的方法,补充了ITER项目目前所遵循的方法,用于建造管理和验证这种复杂组件的校准阶段。第一阶段是确定驱动ITER组件对齐的关键组件要求。然后,按照适当的命名规则清晰地组织需求收集的数据库,并且确实建立了用于数据收集和分析的体系结构。提出了四个虚拟装配试点研究,以显示该方法如何有助于评估已定义的校准场景中的装配要求。
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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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