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Code of a Tokamak Fusion Energy Facility ITER

[+] Author Affiliations
Yasuhide Asada

Central Research Institute of Electric Power Industry, Tokyo, Japan

Kenzo Miya

Keio University, Tokyo, Japan

Kazuhiko Hada, Eisuke Tada

Japan Atomic Energy Research Institute, Ibaraki, Japan

Paper No. ICONE10-22673, pp. 583-590; 8 pages
  • 10th International Conference on Nuclear Engineering
  • 10th International Conference on Nuclear Engineering, Volume 4
  • Arlington, Virginia, USA, April 14–18, 2002
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-3598-7 | eISBN: 0-7918-3589-8
  • Copyright © 2002 by ASME


The technical structural code for ITER (I nternational T hermonuclear E xperimental Fusion R eactor) and, as more generic applications, for D-T burning fusion power facilities (hereafter, Fusion Code) should be innovative because of their quite different features of safety and mechanical components from nuclear fission reactors, and the necessity of introducing several new fabrication and examination technologies. Introduction of such newly developed technologies as inspection-free automatic welding into the Fusion Code is rationalized by a pilot application of a new code concept of “system-based code for integrity”. The code concept means an integration of element technical items necessary for construction, operation and maintenance of mechanical components of fusion power facilities into a single system to attain an optimization of the total margin of these components. Unique and innovative items of the Fusion Code are typically as follows; • Use of non-metals; • Cryogenic application; • New design margins on allowable stresses, and other new design rules; • Use of inspection-free automatic welding, and other newly developed fabrication technologies; • Graded approach of quality assurance standard to cover radiological safety-system components as well as non-safety-system components; • Consideration on replacement components.

Copyright © 2002 by ASME



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