Engineering design of the ITER blanket and relevant research and development results

• Published in: Fusion engineering and design Vol. 46; no. 2; pp. 159 - 175
• Main Authors: Elio, F, Ioki, K, Barabaschi, P, Bruno, L, Cardella, A, Hechler, M, Kodama, T, Lodato, A, Loesser, D, Lousteau, D, Miki, N, Mohri, K, Parker, R, Raffray, R, Williamson, D, Yamada, M, Daenner, W, Mattas, R, Strebkov, Y, Takatsu, H
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01.11.1999; New York, NY Elsevier Science
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Installations for energy generation and conversion: thermal and electrical energy; ITER blanket; Research and development; Research and development; ITER blanket; R and D program; Tokamak; Nuclear fusion reactor; Construction; Design criterion; Blanket; State of the art; Prototype; Hot isostatic pressing; Surface plasma interaction
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/S0920-3796(99)00043-5

The design of the ITER blanket is presented together with the related technology which has been developed. The evolution of this component since the beginning of the EDA is explained in relation to the developing understanding of the thermal deformations and of the electromagnetic forces. These loads lead to a system composed of compact modules protecting a continuous support shell called a backplate. The backplate is a stiff double wall construction which conveys the coolant to the modules. The supports of the module are flexible and allow relative thermal expansions. They are connected and disconnected to the backplate by bolts operated through holes in the front face of the module. The coolant connections and the electrical straps located on the back of the modules are reached similarly. The first wall is integral with the module and cooled in series. A research and development program on materials and joining methods defined the construction path which has been tested in prototypes. The main body is built of stainless steel by forging and drilling or powder hot isostatic pressing (HIP), depending on the complexity of the shape. The first wall includes a dispersion strengthened copper heat sink which is hot isostatic pressed onto the steel body. Beryllium is the basic plasma facing material and is attached by HIP to the copper. Prototypes of the module attachment have been built and are under integrated tests.