Contributions to the International Symposium on Fusion Nuclear Technology (Tokyo, 10-19 April 1988)
This report contains the proceedings of a symposium on fusion nuclear technology. The first paper deals with a ceramic breeder in a poloidal tube blanket for a Tokomak reactor. Tritium breeding capabilities together with system reliability are taken as the main design criteria. The second paper describes the joint ENEA-AMSALDO design and manufacturing feasibility study of a brazed first wall for NET. The reference design is based on the use of flat plates coupled by nicrobrazing to water poloidal cooling tubes. The paper reports on the related design work and the results of the studies performed.
Bibliographic Reference: Report: RT/FUS/88/1 EN (1988)
Availability: Available from Servizio Studi e Documentazione, ENEA, Centro Ricerche Energia Frascati, C.P. 65-00044 Frascati, Roma (IT)
Record Number: 198910104 / Last updated on: 1994-12-01
Original language: en
Available languages: en