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| 001 | 844548 | ||
| 005 | 20240711113539.0 | ||
| 024 | 7 | _ | |a 10.1016/j.fusengdes.2017.01.009 |2 doi |
| 024 | 7 | _ | |a 0920-3796 |2 ISSN |
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| 100 | 1 | _ | |a Biel, W. |0 P:(DE-Juel1)129967 |b 0 |e Corresponding author |u fzj |
| 245 | _ | _ | |a Systems code studies on the optimization of design parameters for a pulsed DEMO tokamak reactor |
| 260 | _ | _ | |a New York, NY [u.a.] |c 2017 |b Elsevier |
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| 520 | _ | _ | |a In the European strategy towards fusion power, a demonstration tokamak fusion reactor (DEMO) is foreseen as the next single step between ITER and a power plant. The current baseline concept is a tokamak reactor with net electrical output power of Pel ∼ 500 MW and plasma pulse duration of tpulse ∼2 h. Systems codes are commonly used in the design process as numerical tools for optimization studies. The key performance data of the reactor such as Pel and tpulse are depending on a variety of design and plasma parameters. In the application of systems codes within this multi-dimensional parameter space, a clear quantitative understanding of the most suitable optimization criteria has to be developed, and various physics and technology limits should be obeyed to obtain meaningful results.In this work we use a fusion reactor systems code to perform parameter variations for a pulsed DEMO tokamak reactor. Various output quantities are presented as a basis for the quantitative assessment of the numerical results, and options for a further development of the current DEMO baseline design are proposed and briefly discussed. |
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| 700 | 1 | _ | |a Zohm, H. |0 P:(DE-HGF)0 |b 4 |
| 773 | _ | _ | |a 10.1016/j.fusengdes.2017.01.009 |g Vol. 123, p. 206 - 211 |0 PERI:(DE-600)1492280-0 |p 206 - 211 |t Fusion engineering and design |v 123 |y 2017 |x 0920-3796 |
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