Virtual simulator for the ITER Agile Robot Transporter with an inverse kinematic algorithm considering joint limits and collision avoidance

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Chang-Hwan Choi , Jonas Kynde , Soumik Sarkar , David Hamilton , Raphael Hery , Jim Palmer
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引用次数: 0

Abstract

Remote Handling (RH) systems are required to maintain the in-vessel components inside the ITER Vacuum Vessel (VV) because of high radiation. The Agile Robot Transporter (ART) is under development to cope with the in-vessel maintenance needs. This paper describes a virtual simulator of the Transporter to verify its kinematics such as joint ranges and body lengths whether it is suitable to carry out the blanket first wall maintenance. Independent joint control and sequential joint control algorithms are implemented, which are used to simulate the deployment sequence of the Transporter. End-effector control, null space control, automatic trajectory generation and control algorithms are implemented by using inverse kinematic algorithms, which are used to produce various postures of the Transporter to access the blanket first walls. The control algorithms consider the physical constraints such as the joint limits, internal collision avoidance among the Transporter’s bodies, and external collision avoidance between the Transporter’s bodies and the blanket first walls. The simulation results demonstrate that the Transporter can be deployed from the port into the VV and it can access all blanket first walls while respecting the physical constraints.
由于高辐射,ITER 真空容器 (VV) 内的舱内组件需要远程处理 (RH) 系统进行维护。目前正在开发敏捷机器人运输车 (ART),以满足舱内维护需求。本文介绍了运输机的虚拟仿真器,以验证其运动学特性,如关节范围和身体长度是否适合进行毯子第一壁维护。实现了独立关节控制和顺序关节控制算法,用于模拟运输船的部署顺序。末端执行器控制、无效空间控制、自动轨迹生成和控制算法是通过使用逆运动学算法来实现的,这些算法用于生成 "运输机 "的各种姿态,以便进入第一道毯墙。控制算法考虑了物理约束条件,如关节限制、运输机机体之间的内部碰撞规避以及运输机机体与毯子第一层墙壁之间的外部碰撞规避。仿真结果表明,运输机可以从端口部署到 VV 中,并且可以在遵守物理约束的情况下进入所有第一毯墙。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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