Title :
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
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;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635371
