DocumentCode :
1606431
Title :
Design analysis and manufacturing studies for ITER In-Vessel Coils
Author :
Kalish, M. ; Brooks, A. ; Heitzenroeder, P. ; Neumeyer, C. ; Titus, P. ; Zhai, Yujia ; Zatz, I. ; Messineo, M. ; Gomez, M. ; Hause, C. ; Daly, Eamonn ; Martin, Andrew ; Wu, Yaowu ; Jin, J. ; Long, F. ; Song, Yuning ; Wang, Zhen ; Zan Yun ; Hsiao, J. ; Pil
Author_Institution :
Princeton Plasma Phys. Lab., Princeton, NJ, USA
fYear :
2013
Firstpage :
1
Lastpage :
6
Abstract :
ITER is incorporating two types of In Vessel Coils (IVCs): ELM Coils to mitigate Edge Localized Modes and VS Coils to provide Vertical Stabilization of the plasma. Strong coupling with the plasma is required so that the ELM and VS Coils can meet their performance requirements. Accordingly, the IVCs are in close proximity to the plasma, mounted just behind the Blanket Shield Modules. This location results in a radiation and temperature environment that is severe necessitating new solutions for material selection as well as challenging analysis and design solutions. Fitting the coil systems in between the blanket shield modules and the vacuum vessel leads to difficult integration with diagnostic cabling and cooling water manifolds. The design of the IVCs is now progressing towards a final design scheduled for late CY 13. The project is a collaboration between the Princeton Plasma Physics Laboratory in Princeton NJ, the Chinese Academy of Sciences (ASIPP) in Hefei China and the ITER Organization. An extensive thermal and stress analysis to evaluate the effects of the high temperatures and electromagnetic loads on the In Vessel Coils has been undertaken. Manufacturing development is underway at ASIPP to develop the processes necessary to build ELM coil and VS Coil prototypes. This paper will outline the design and analysis issues as well as review the manufacturing development required to address these requirements and plans for prototypes.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor design; plasma boundary layers; plasma diagnostics; plasma toroidal confinement; ASIPP; Chinese Academy of Sciences; ELM coils; Hefei China; ITER in-vessel coil design analysis; Princeton Plasma Physics Laboratory; blanket shield modules; cooling water manifold; edge localized modes; electromagnetic loads; material selection; plasma diagnostic cabling manifold; plasma radiation environment; plasma temperature; plasma vertical stabilization; stress analysis; thermal analysis; Cable insulation; Coils; Compaction; Conductors; Joints; Minerals; Prototypes; ELM; Edge Localized Modes; ITER; IVC; In Vessel Coils; Magnesium Oxide Insulation; MgO; Mineral Insulated Conductor; SSMIC; Stainless Steel Mineral Insulated Conductor; VS; Vertical Stabilization;
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.2013.6635400
Filename :
6635400
Link To Document :
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