% IMPORTANT: The following is UTF-8 encoded. This means that in the presence % of non-ASCII characters, it will not work with BibTeX 0.99 or older. % Instead, you should use an up-to-date BibTeX implementation like “bibtex8” or % “biber”. @ARTICLE{Zohm:860633, author = {Zohm, H. and Träuble, F. and Biel, W. and Fable, E. and Kemp, R. and Lux, H. and Siccinio, M. and Wenninger, R.}, title = {{A} stepladder approach to a tokamak fusion power plant}, journal = {Nuclear fusion}, volume = {57}, number = {8}, issn = {1741-4326}, address = {Vienna}, publisher = {IAEA}, reportid = {FZJ-2019-01306}, pages = {086002 -}, year = {2017}, abstract = {We present an approach to design in a consistent way a stepladder connecting ITER, DEMO and an FPP, starting from an attractive FPP and then locating DEMO such that main similarity parameters for the core scenario are constant. The approach presented suggests how to use ITER such that DEMO can be extrapolated with maximum confidence and a development path for plasma scenarios in ITER follows from our approach, moving from low β N and q typical for the present Q = 10 scenario to higher values needed for steady state. A numerical example is given, indicative of the feasibility of the approach, and it is backed up by more detailed 1.5-D calculation using the ASTRA code. We note that ideal MHD stability analysis of the DEMO operating point indicates that it is located between the no-wall and the ideal wall β-limit, which may require active stabilization. The DEMO design could also be a pulsed fallback solution should a stationary operation turn out to be impossible.}, cin = {IEK-4}, ddc = {620}, cid = {I:(DE-Juel1)IEK-4-20101013}, pnm = {174 - Plasma-Wall-Interaction (POF3-174)}, pid = {G:(DE-HGF)POF3-174}, typ = {PUB:(DE-HGF)16}, UT = {WOS:000403340600001}, doi = {10.1088/1741-4326/aa739e}, url = {https://juser.fz-juelich.de/record/860633}, }