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Abstract

The neutronic problems faced in the conceptual design of the INTOR experimental fusion reactor, are reviewed and examined in this paper. Three main groups of problems are considered: the radiation damage and activation of the first wall, the improvement of the tritium breeding ratio, and the shielding problems. This analysis refers to the breeding blanket containing the eutectic Li-17Pb-83 which has been extensively studied by the European Laboratories and by the JRC in particular. A few critical issues which have not yet been resolved and which require further R & D will be pointed out. The results of this study allow some general considerations, that apply to all TOKAMAK Fusion Reactors, about the achievements of an adequate tritium breeding ratio, and the choice of structural materials.

Additional information

Authors: PONTI C JRC ISPRA ESTAB. (ITALY), JRC ISPRA ESTAB. (ITALY)
Bibliographic Reference: WORKSHOP ON FUSION BLANKET TECHNOLOGY, ERICE (ITALY), JUNE 5-11, 1983. AVAILABILITY: CEC LUXEMBOURG, DG XIII/A2 MENTIONING PAPER E 31023 ORA
Availability: Can be ordered online
Record Number: 1989122005500 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en