Systems Analysis of INTOR-Like Designs Based on a Simplified Rescaling Method

摘要

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 Two A 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 multiparamter 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 Two A Part 3 workshop. An outlook is added on what a next-step parameter set could look like on the basis of modified physics input assumptions as adopted towards the end of the INTOR studies and no longer taken into account by them. (ERA citation 14:002603)