Simulated installation of a breeding blanket segment in a two-port mover context

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Petri Tikka, Hannu Saarinen, Hannu Martikainen, William Brace, Janne Lyytinen
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引用次数: 0

Abstract

The abstract relates to work undertaken on the Two Port Mover (TPM) Remote Maintenance (RM) concept in European DEMO. The focus of the study was to assess the operational procedures for installing the Blanket Leg Unit and Lower Port Winch of the Two-Port Mover. In addition, alternative means for constraining the rotations of the breeding blanket during the removal and installation process of blankets were studied.
The Two-Port Mover was tested in a dynamic simulation. The assessment process was carried out by using a Unity game-engine in a combination of AGX Dynamics for Unity plugin. The scope was to utilize virtual prototyping to visualize how the cabling of the studied Lower Port winch approach would interact within the Vacuum Vessel sector. Dynamic physics enables the cabling and the interface plate to collide with the surrounding environment and proper adjustments to the performed procedures can be validated already in the early stages of the design process. The final connection with the interface plate and the winches is performed by a remotely operated manipulator in a virtual environment. In the context of this simulation, the manipulator was controlled with a haptic device. This ensured precise control of the connection process, but also demonstrated how the cables would interact while operating the manipulator. Thus, influencing initial TPM design maturity.

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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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