DESIGN OF A TRITIUM BREEDING BLANKET FOR VOLUMETRIC NEUTRON SOURCE

Citation
Y. Asaoka et al., DESIGN OF A TRITIUM BREEDING BLANKET FOR VOLUMETRIC NEUTRON SOURCE, Fusion engineering and design, 41, 1998, pp. 477-484
Citations number
11
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
09203796
Volume
41
Year of publication
1998
Pages
477 - 484
Database
ISI
SICI code
0920-3796(1998)41:<477:DOATBB>2.0.ZU;2-K
Abstract
A water-cooled and austenitic stainless-steel-structured breeding blan ket system is designed for a volumetric neutron source (VNS), based on a steady-state tokamak device. The designed VNS with super-conducting coils has a 4.5 m main radius and a total of 300 MW in fusion power. It yields the tritium consumption of approximately 10 kg per year with 50% availability. It is unrealistic to assume that this amount of tri tium could be supplied by other nuclear facilities, therefore, tritium breeding with the VNS device itself should be accommodated. The capab ility of tritium breeding for the Li-Pb breeder is examined. Compared to ceramic breeding materials, in general, the Li,,Pb,, breeder has th e potential for a higher tritium breeding ratio. In addition, the comp atibility of Li-Pb with water coolant and with structure material at l ow temperature and low flow velocity may be acceptable. The calculated local TBR in the present design reached 1.4 or more in the Li-Pb bree der with a sufficient thickness of the breeding zone. The temperature distribution in the breeding region of the Li-Pb blanket was controlle d to avoid corrosion of the structure material, using a double-walled cooling panel. The net TBR might attain the acceptable value when only the outboard Li-Pb blanket is used, since the contribution of outboar d blanket to tritium breeding is higher than its coverage. (C) 1998 El sevier Science S.A. All rights reserved.