A new trial of tokamak in-vessel inspection manipulator
Creators
Description
In this paper, we discuss the design and partial implementation of an in-vessel inspection manipulator in detail, which is considered to serve for China's Experimental Advanced Superconducting Tokamak (EAST). Besides the ordinary kinematic/dynamic constraints and specifications for a multiple degrees of freedom (DOF) manipulator suitable for EAST in-vessel inspection, there is extra necessity in design for the extreme in-vessel environment, e.g., high temperature and high vacuum. Based on our recent developed active cooling system, a specific proposal is explored, which employs ordinary commercial mechanical/electrical components only, as if the manipulator works in normal temperature environment. This paper also emphasizes some challenging technical issues toward an implementation, such as an optimization of thermal gradient/cooling path in the manipulator, a trade-off between large reachable space and large rotation angle of each joint, a special designed revolute joint structure for cooling tube arrangement and so on. We use an EtherCAT based real time control platform connecting drivers and sensors, which achieves a robust closed-loop system and a clean cable aspect simultaneously. In the later part of the paper, basic mechanical tests and inspection process are described. Evaluation on recent progress and future work toward a whole-scale test is stated and expected.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2015.06.164Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2015.06.164;
- PII
- S0920-3796(15)30222-2;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 98-99
- Journal Page Range
- p. 1701-1705
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 28. symposium on fusion technology
- Acronym
- SOFT-28
- Dates
- 29 Sep - 3 Oct 2014
- Place
- San Sebastian (Spain)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48006689
- Subject category
- S42: ENGINEERING; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CABLES; CHINA; CONTAINERS; CONTROL; COOLING; COOLING SYSTEMS; DEGREES OF FREEDOM; DESIGN; HT-7U TOKAMAK; MANIPULATORS; MECHANICAL TESTS; OPTIMIZATION; PRESSURE RANGE MICRO PA; REMOTE HANDLING; SENSORS; TEMPERATURE GRADIENTS; TEMPERATURE RANGE 0400-1000 K; TUBES
- Descriptors DEC
- ASIA; CLOSED PLASMA DEVICES; ENERGY SYSTEMS; EQUIPMENT; LABORATORY EQUIPMENT; MATERIALS HANDLING EQUIPMENT; MATERIALS TESTING; PRESSURE RANGE; REMOTE HANDLING EQUIPMENT; TEMPERATURE RANGE; TESTING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.