Safety related R&D for the ITER baseline design

Author

Reyes, S. ; Taylor, N. ; Cortes, P. ; Ciattaglia, S. ; Rosanvallon, S. ; Perevezentsev, A. ; Iseli, M. ; Baker, D. ; Elbez-Uzan, J. ; Topilski, L. ; Gulden, W. ; Sharpe, P. ; Hayashi, T.

Author_Institution

ITER Organ., St. Paul-lez-Durance, France

fYear

2009

fDate

1-5 June 2009

Firstpage

1

Lastpage

6

Abstract

This paper presents an overview of the safety related operating feedback taken into account in the ITER baseline design, and of the previously completed and ongoing Research and Development (R&D) activities in support of ITER safety analyses. Operating feedback relevant to ITER mostly comes from previous and currently existing fusion devices, and from the operation of tritium laboratories. Regarding the safety related R&D, since the early times of the ITER project, an extensive program has been devoted to understanding the issues, gathering data on source terms, modeling underlying phenomena, and developing analytical tools for safety analysis.

Keywords

Tokamak devices; fusion reactor design; fusion reactor fuel; fusion reactor operation; fusion reactor safety; radioactive waste; research and development; tritium; tritium handling; ITER baseline design; fuel cycles; fusion devices; reactor operation; research and development; safety; tritium laboratories; waste management; Accidents; Effluents; Feedback; Hazards; Laboratories; Research and development; Safety; Tokamaks; Variable speed drives; Waste management; ITER; R&D; fusion; safety;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on

Conference_Location

San Diego, CA

Print_ISBN

978-1-4244-2635-5

Electronic_ISBN

978-1-4244-2636-2

Type

conf

DOI

10.1109/FUSION.2009.5226518

Filename

5226518