DocumentCode
1947431
Title
Design feasibility analysis of the robot for EAST tokamak flexible in-vessel inspection
Author
Peng, X. ; Song, Y. ; Yang, Y. ; Qiao, P. ; Ji, X.
Author_Institution
Inst. of Plasma Phys., Hefei, China
fYear
2011
fDate
26-30 June 2011
Firstpage
1
Lastpage
4
Abstract
EAST is a full superconducting tokamak fusion experiment device with `D´ shape vacuum vessel and toroidal coils and actively cooled plasma facing components (PFCs), which aims at studying the scientific and engineering issues under steady state operation. It is difficult but very important to know well the operating state of the components in the vacuum vessel during plasma operation campaign for the help of guiding operation plan and understanding physical phenomena. A robotic system (called flexible in-vessel inspection robot, FIVIR) is proposed to inspect the surface of plasma facing components to know the performance of first wall, such as erosion and desquamation. Because of the geometric requirement and the intensity of ports usage arrangement, two FIVIRs are planned installing toroidal symmetry on EAST. Each FIVIR is a series-wound robot with ten degrees of freedom consisting of main robot and end-effector. The main robot has the primary function that transports the end-effector and associated process tools into the vacuum chamber in the equatorial plane at R=1.94m and back to the storage port, which has the benefit that easy control of the FIVIR and easy position calculation of the end-effector. All the joints in the FIVR are driven by actuators. The workspace of the robot is analyzed to see whether it can reach any point of the plasma facing surface in the distance of 15mm and the range of ±90°along toroidal direction.
Keywords
Tokamak devices; fusion reactor design; fusion reactor materials; plasma toroidal confinement; plasma-wall interactions; D shape vacuum vessel; EAST tokamak; FIVIR; actively cooled plasma facing components; design feasibility analysis; equatorial plane; flexible in-vessel inspection; full superconducting tokamak fusion experiment; plasma facing surface; plasma operation campaign; steady state operation; toroidal coils; toroidal symmetry; vacuum chamber; Humans; Robots; EAST; feasibility analysis; in-vessel inspection; robot;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location
Chicago, IL
ISSN
1078-8891
Print_ISBN
978-1-4577-0669-1
Electronic_ISBN
1078-8891
Type
conf
DOI
10.1109/SOFE.2011.6052217
Filename
6052217
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