Structural design problems for the first wall/blanket system of fusion reactors
The paper consists of two sections, one devoted to experimental fusion reactors and the other concerned with a demonstration plant. An overview of structural design problems for the in-vessel components of ITER is presented first. ITER design guidelines, features and concepts for first wall, shielding/breeding blanket and divertor are described, with special reference to metallic components. Emphasis is placed on the operating conditions of the various components undergoing the combined effects of thermal, mechanical and electromagnetic loads. Subsequently, structural design problems for the tritium breeding blanket of a fusion reactor are outlined, with special reference to blanket designs for a demonstration reactor (DEMO) based on the use of ceramic breeder materials.
Bibliographic Reference: Report: RT/NUCL/90/23 EN (1990) 24 pp.
Availability: Available from Servizio Studi e Documentazione, ENEA, Centro Ricerche Energia Frascati, C.P. 65-00044 Frascati, Roma (IT)
Record Number: 199210221 / Last updated on: 1994-12-02
Original language: en
Available languages: en