Design Analysis and Manufacturing Studies for ITER In-Vessel Coils
- Princeton Plasma Physics Lab., Princeton, NJ (United States)
- ITER Organization, St. Paul-lez-Duranace (France)
- Chinese Academy of Sciences, Anhui (China). Institute of Plasma Physics
- Vector Resources, Annandale, VA (United States)
- Sherbrooke Consulting, Arlington, VA (United States)
- Univ. of Wisconsin-Madison, WI (United States). Fustion Technology Institute
- Southwestern Institute of Physics, Chengdu (China)
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.
- Research Organization:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Organization:
- USDOE Office of Science (SC)
- DOE Contract Number:
- DE-ACO2-09CH11466
- OSTI ID:
- 1088215
- Report Number(s):
- PPPL-4923
- Resource Relation:
- Conference: 25th Symposium on Fusion Engineering, San Francisco, CA (United States), 10-14 June 2013; Related Information: In: SOFE 2013 Proceedings (June 0213)
- Country of Publication:
- United States
- Language:
- English
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