A fail–safe and cost effective fabrication route for blanket First Walls

• Published in: Journal of nuclear materials 2013-11, Vol.442 (1-3), p.538-541
• Main Authors: Commin, L., Rieth, M., Dafferner, B., Zimmermann, H., Bolich, D., Baumgärtner, S., Ziegler, R., Dichiser, S., Fabry, T., Fischer, S., Hildebrand, W., Palussek, O., Ritz, H., Sponda, A.
• Format: Article
• Language: English
• Subjects: Activation; Assembly; Blanketing; Channels; Fusion welding; Helium cooled; Plates; Walls
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2013.07.043

Helium Cooled Lithium Lead and Helium Cooled Pebble Bed concepts have been selected as European Test Blanket Modules (TBM) for ITER. The TBM fabrication will need the assembly of six Reduced Activation Ferritic Martensitic steel sub-components, namely First Wall, Caps, Stiffening Grid, Breeding Units, Back Plates/Manifolds, and Attachment system. The fabrication of the First Wall requires the production of cooling channels inside 30mm thick bended plates. For this specific component, the main issues consist of the lack of accessibility of some areas to join, the process tolerances, the dimensional stability and the resulting assembly mechanical properties. Several fabrication routes have been already investigated, which involve diffusion welding and fusion welding (electron beam, laser beam, hybrid MIG/laser). In this study, an alternative processing method was developed, based on Hot Isostatic Pressing of inner pipes within two half-shells. This method presents some major advantages over the existing ones, in particular its inherent fail–safe design due to the application of the double containment principle, the solely use of cost effective standard fabrication processes and the resulting component dimensional stability. A four channel mock-up was fabricated and analyzed to validate the fabrication procedure. The joint quality was assessed using microstructural characterization and Charpy tests. The results confirm the predicted perfect weld lines as well as the preservation of the mechanical properties. Therefore, the presented fabrication procedure is very appropriate for the fabrication of First Walls for fusion reactor blankets.