A DEMONSTRATION TOKAMAK REACTOR - ASPECTS OF THE CONCEPTUAL DESIGN
Some of the more important aspects of the design of a 600 MW(e) demonstration tokamak reactor are discussed with particular emphasis on the design of the tritium breeding blanket and its associated components. Alternative blanket designs employing ceramic and liquid breeding materials are presented. Both conform to the requirements of a commercial reactor in having a global tritium breeding ratio greater than unity and an outlet coolant temperature high enough for efficient electricity generation. Solutions to the problems of heat loading and plasma erosion of the first wall and divertor plates are proposed.
Bibliographic Reference: 10TH INTERNATIONAL CONFERENCE ON PLASMA PHYSICS AND CONTROLLED NUCLEAR FUSION RESEARCH, LONDON (UK), SEPT. 12 - 19, 1984 PUBLISHED BY IAEA, WIEN (AUSTRIA), 1985, VOL. 3, PP. 269-277
Record Number: 1989124049800 / Last updated on: 1987-01-01
Available languages: en