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(FTP/29) Design and Development of Ceramic Breeder Demo Blanket

M. Enoeda, S. Sato, T. Hatano, K. Furuya, M. Kanari, T. Abe, T. Kuroda, S. Hara, S. Kikuchi, H. Takatsu, S. Tanaka¹

Blanket Engineering Laboratory, Japan Atomic Energy Research Institute, Naka-machi, Naka-gun, Ibaraki-ken, 311-0193 Japan
¹ Dep. of Quantum Engineering and Systems Sciences, the University of Tokyo, Japan

Abstract.  Ceramic breeder blanket development has been widely conducted in Japan from fundamental researches to project-oriented engineering scaled development. A long term R&D program has been launched in JAERI since 1996 as a course of DEMO blanket development. The objectives of this program are to provide engineering data base and fabrication technologies of the DEMO blanket, aiming at module testing in ITER currently scheduled to start from the beginning of the ITER operation as a near-term target. Two types of DEMO blanket systems, water cooled blanket and helium cooled blanket, have been designed to be consistent with the SSTR (Steady State Tokamak Reactor) which is the reference DEMO reactor design in JAERI. Both of them utilize packed small pebbles of breeder Li₂O or Li₂TiO₃ as a candidate) and neutron multiplier (Be) and rely on the development of advanced structural materials (a reduced activation ferritic steel F82H) compatible with high temperature operation.

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