Manufacture of blanket shield modules for ITER

• Published in: Fusion engineering and design Vol. 75; pp. 291 - 296
• Main Authors: Lorenzetto, P., Boireau, B., Boudot, C., Bucci, P., Furmanek, A., Ioki, K., Liimatainen, J., Peacock, A., Sherlock, P., Tähtinen, S.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01.11.2005; New York, NY Elsevier Science
• Subjects: Applied sciences; Beryllium; Controled nuclear fusion plants; Cu alloy; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fabrication; Installations for energy generation and conversion: thermal and electrical energy; ITER blanket shield module; Fabrication; Cu alloy; Beryllium; ITER blanket shield module; Tokamak; Nuclear fusion reactor; Blanket; Shield; Farbrication; Beryllim; First wall
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2005.06.277

A research and development programme for the ITER blanket shield modules has been implemented in Europe to provide input for the design and the manufacture of the full-scale production components. It involves in particular the fabrication and testing of mock-ups (small scale and medium scale) and full-scale prototypes of shield blocks (SB) and first wall (FW) panels. The manufacturing feasibility of FW panels has been demonstrated for two copper alloy candidates. Two designs have been developed for the manufacture of the SB, one for a conventional fabrication route and one for a fabrication route based on the hot isostatic press technology. This paper presents the fabrication routes developed in Europe for the manufacture of the ITER Shield modules.