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Tritium Breeding Blanket

D. Smith, M. Billone, Y. Gohar, A. Raffray, W. Daenner, D. Lorenzetto, C. Baker, I. Sviatoslavsky, A. Anitipenkov, A. Siderov, S. Mori, T. Kuroda, K. Maki, H. Takatsu, H. Yoshida, G. Simbolotti, G. Shatalov

Fusion Science and Technology / Volume 19 / Number 3P2B / May 1991 / Pages 1424-1431

ITER / Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) / dx.doi.org/10.13182/FST91-A29542

The terms of reference for ITER provide for incorporation of a tritium breeding blanket with a breeding ratio as close to unity as practical.1–4 A breeding blanket is required to assure an adequate supply of tritium to meet the program objectives. Based on specified design criteria, a ceramic breeder concept with water coolant and an austenitic steel structure has been selected as the first option and lithium-lead blanket concept has been chosen as an alternate option. The first wall, blanket, and shield are integrated into a single unit with separate cooling systems. The design makes extensive use of beryllium to enhance the tritium breeding ratio. The design goals with a tritium breeding ratio of 0.8–0.9 have been achieved and the R&D requirements to qualify the design have been identified.