ITER blanket engineering challenges and solutions

Author

Raffray, A.R. ; Calcagno, B. ; Chappuis, P. ; Dellopoulos, G. ; Zhang Fu ; Jiming, Chen ; Kim, D.H. ; Kim, Sang Wu ; Khomiakov, S. ; Labusov, A. ; Martin, Andrew ; Merola, M. ; Mitteau, R. ; Ulrickson, Mike

Author_Institution

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

fYear

2013

Firstpage

1

Lastpage

8

Abstract

The ITER blanket design process is very challenging due to demanding design and interface requirements and constraints, including high heat fluxes from the plasma, large electromagnetic loads during off-normal events, sufficient contribution to the shielding of the vacuum vessel and superconducting coils, and tight interfacing space constraints with many key components. This paper highlights some of these challenges and the associated solutions developed as part of the final blanket design effort.

Keywords

Tokamak devices; fusion reactor blankets; fusion reactor design; plasma toroidal confinement; shielding; superconducting coils; ITER blanket design process; ITER blanket engineering challenges; ITER blanket engineering solutions; design requirement; final blanket design effort; high heat fluxes; interface requirement; large electromagnetic loads; off-normal events; superconducting coils; vacuum vessel shielding; Coatings; Fasteners; Fingers; Heat sinks; Heating; Plasmas; Steel; ITER; blanket; electromagnetic loads; high heat flux; interface; shielding;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on

Conference_Location

San Francisco, CA

Print_ISBN

978-1-4799-0169-2

Type

conf

DOI

10.1109/SOFE.2013.6635371

Filename

6635371