Design and analysis of the structural components in the ITER ECH upper port plug

The structural components of the ITER ECH upper port plug are presented which integrates the mm-wave beam lines of the front steering launcher for the control of plasma instabilities. The design of the main structure considers two alternatives. Firstly, a double wall configuration for the port plug...

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Bibliographic Details
Published in:	Fusion engineering and design Vol. 82; no. 5; pp. 700 - 708
Main Authors:	Späh, P., Heidinger, R., Hailfinger, G., Henderson, M., K.Kleefeldt, Serikov, A., Ciattaglia, E., Saibene, G.
Format:	Journal Article Conference Proceeding
Language:	English
Published:	Amsterdam Elsevier B.V 01-10-2007 New York, NY Elsevier Science
Subjects:	Applied sciences Controled nuclear fusion plants ECRH Energy Energy. Thermal use of fuels Exact sciences and technology Installations for energy generation and conversion: thermal and electrical energy Neutronics analysis System engineering Thermo-mechanical analysis Upper port plug System engineering Upper port plug ECRH Thermo-mechanical analysis Neutronics analysis Tokamak Plasma Cooling Shield Nuclear fusion reactor Blanket Nuclear radiation Instability ECR heating Plasma heating First wall
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Summary:	The structural components of the ITER ECH upper port plug are presented which integrates the mm-wave beam lines of the front steering launcher for the control of plasma instabilities. The design of the main structure considers two alternatives. Firstly, a double wall configuration for the port plug frame responds to homogeneous baking requirements at 240 °C. Secondly, an alternative frame is presented with a single wall in sections that do not require active cooling. The blanket shield module (BSM) is designed as a double-wall housing with a first wall panel (FWP) and individual shield blocks respecting the open space for the mm-wave beams. The cut-out sections to the design of the FWP and the neighbouring lower regular blanket module are defined for the beams of the actual front steering model. The thermo-mechanical stresses of the FWP and the BSM housing caused by nuclear heating and plasma radiation were analysed for the more severe case of the earlier remote steering (“3/8 RS”) reference model. As a result of the calculations for stationary loads and for transient loads during a typical plasma burn of 400 s, no critical stresses have to be expected in the BSM housing.
Bibliography:	SourceType-Scholarly Journals-2 ObjectType-Feature-2 ObjectType-Conference Paper-1 content type line 23 SourceType-Conference Papers & Proceedings-1 ObjectType-Article-3
ISSN:	0920-3796 1873-7196
DOI:	10.1016/j.fusengdes.2007.01.009