The WEST project mechanical analysis of the divertor structure according to the nuclear construction code

• Published in: Fusion engineering and design Vol. 89; no. 7-8; pp. 1832 - 1835
• Main Authors: Larroque, S., Portafaix, C., Saille, A., Doceul, L., Bucalossi, J., Samaille, F., de Freslon, S.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.10.2014
• Subjects: Coils; Construction; Design engineering; Devices; Mechanical analysis; Nuclear fusion; RCCMR; Structure; Three dimensional; Tungsten; WEST; RCCMR; Structure; WEST; Mechanical analysis
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2014.02.073

•Divertor structure is mainly loaded by electromagnetical forces.•A simplified FEM analysis give the stresses in the structure.•RCCM criteria are required for the sizing.•Refined finite element models are used for local overstresses. The Tore Supra tokamak is being transformed in an x-point divertor fusion device in the frame of the WEST project, launched in support to the ITER tungsten divertor strategy. The installation of coils inside the vacuum vessel led to the design of a divertor supporting platform able to meet the project requirements and the associated electromagnetic loads. This paper illustrates the design, the method and the results of the thermomechanical elastic stress analyses performed in 2012. The validation of the integrity of the structure is based on the compliance with RCCMR design criteria (even though these Design and Construction rules for Mechanical Components of nuclear installations are not required for such experimental fusion device). Several 3D analyses are performed with the ANSYS code. The major one is a global analysis of half structure which determinates the stresses in the main part of the components. It gives an idea of the areas which needs local analyses. It also provides the interface loads for junction studies or simplified local model.