Community Research and Development Information Service - CORDIS

Abstract

On the basis of a simplified non-optimizing rescaling method the INTOR-like next-step tokamak reactor designs, NET-DN, FER, TIBER II and OTR (as of March 1987), are analysed and compared with each other and with INTOR, as of Phase IIA Part 2, on a common basis in order to understand their characteristic differences deriving from the respective input assumptions. Always on the basis of a certain confinement scaling, this is done with different approaches. It is generally seen that the physics input assumptions and their respective combination play a major role, with the maximum toroidal field and the central solenoid radius also being influential. Depending on the set of physics/engineering input assumptions in combination with the set of design parameters required, a certain domain in multiparameter space becomes accessible from which a choice could be made (e.g. to optimize cost for a certain fusion power). The results referring to typical INTOR assumptions and requirements were also contributed to the INTOR Phase IIA Part 3 workshop.

Additional information

Authors: KNOBLOCK A F MAX-PLANCK-INSTITUT FUER PLASMAPHYSIK, GARCHING BEI MUENCHEN (GERMANY), MAX-PLANCK-INSTITUT FUER PLASMAPHYSIK, GARCHING BEI MUENCHEN (GERMANY)
Bibliographic Reference: WRITE TO MAX-PLANCK-INSTITUT FEUR PLASMAPHYSIK, 8046 GARCHING BEI MUENCHEN (GERMANY), MENTIONING REPORT IPP 4/235, 1988
Record Number: 1989126106400 / Last updated on: 1989-06-01
Category: PUBLICATION
Available languages: en