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Primary Design and Operation Analysis of the ITER Transfer Cask System

[+] Author Affiliations
Haitian Wang

Shanghai Jiao Tong University, Shanghai; Jiaying College, Meizhou, Guangdong, China

Ge Li, Shijun Qin

Chinese Academy of Sciences, Hefei, Anhui, China

Paper No. ICONE18-29030, pp. 489-494; 6 pages
doi:10.1115/ICONE18-29030
From:
  • 18th International Conference on Nuclear Engineering
  • 18th International Conference on Nuclear Engineering: Volume 6
  • Xi’an, China, May 17–21, 2010
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4934-7
  • Copyright © 2010 by ASME

abstract

The ITER is an international collaborative project aimed at demonstrating the scientific and technological feasibility of fusion energy for peaceful purposes. China as one of the seven parties takes part in the ITER, and wishes to grasp the remote handling technology, which is one of the four key technologies related to the future fusion reactors for electric power generation. The transfer cask system (TCS) is one subsystem of ITER remote handling system, which provides the means for the remote transfer of (clean/activated/contaminated) in-vessel components and Remote Handling Equipment between Hot Cell Facility and Vacuum Vessel through dedicated galleries and lift in the ITER buildings. The TCS can work in the nuclear radiation environment and can be fully driven by self powered electricity with high energy density batteries. Its driving force is provided by nearly twenty servo motors. The remote handling technology can lay the foundation for developing demonstration nuclear fusion power plant in China on self-reliance. Due to the gamma irradiation and the hazard material in these ITER parts, all required maintenance of the port plug and the inner components are being carried out by the TCS, which offers confinement boundaries to these components. The ITER Tokamak building includes three floors, including upper port level, equatorial port level and lower port level, linked by a lift. Due to limited Tokamak building space which is frozen and can not be changed presently, the TCS penetrates its cable tray for about 300 mm. According to the configuration each port level and the mass of the corresponding plug, the dimensions of the TCS envelope in three levels are different. The basic components and the basic parameters of the TCS are presented. Furthermore, according to each port level configuration and the safety requirement of the TCS, the radius of the curvature with the TCS trajectory is optimized, and a trajectory of each port level is determined by the positioned guidance beacons. At last, the results of the computer aided design (CAD) shows that the present conflict between TCS and Tokamak building can be designed compatible with the proposed variable structure cable tray in the ITER Tokamak building and the TCS based on a fleet of server motor driven system.

Copyright © 2010 by ASME

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