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| 001 | 829752 | ||
| 005 | 20240711113742.0 | ||
| 020 | _ | _ | |a 978-3-95806-216-0 |
| 024 | 7 | _ | |2 Handle |a 2128/14368 |
| 024 | 7 | _ | |2 ISSN |a 1866-1793 |
| 037 | _ | _ | |a FZJ-2017-03386 |
| 041 | _ | _ | |a English |
| 100 | 1 | _ | |0 P:(DE-Juel1)156199 |a Blommaert, Maarten |b 0 |e Corresponding author |g male |u fzj |
| 245 | _ | _ | |a Automated Magnetic Divertor Design for Optimal Power Exhaust |f - 2016-11-21 |
| 260 | _ | _ | |a Jülich |b Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag |c 2017 |
| 300 | _ | _ | |a xxiv, 219 S. |
| 336 | 7 | _ | |2 DataCite |a Output Types/Dissertation |
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| 336 | 7 | _ | |2 BibTeX |a PHDTHESIS |
| 336 | 7 | _ | |0 2 |2 EndNote |a Thesis |
| 336 | 7 | _ | |0 PUB:(DE-HGF)11 |2 PUB:(DE-HGF) |a Dissertation / PhD Thesis |b phd |m phd |s 1494338152_8755 |
| 336 | 7 | _ | |2 DRIVER |a doctoralThesis |
| 490 | 0 | _ | |a Schriften des Forschungszentrums Jülich Reihe Energie & Umwelt / Energy & Environment |v 365 |
| 502 | _ | _ | |a RWTH Aachen University, Diss., 2016n |b Dr. |c RWTH Aachen |d 2016 |
| 520 | _ | _ | |a The so-called divertor is the standard particle and power exhaust system of nuclear fusion tokamaks. In essence, the magnetic configuration hereby `diverts' the plasma to a specific divertor structure. The design of this divertor is still a key issue to be resolved to evolve from experimental fusion tokamaks to commercial power plants. The focus of this dissertation is on one particular design requirement: avoiding excessive heat loads on the divertor structure. The divertor design process is assisted by plasma edge transport codes that simulate the plasma and neutral particle transport in the edge of the reactor. These codes are computationally extremely demanding, not in the least due to the complex collisional processes between plasma and neutrals that lead to strong radiation sinks and macroscopic heat convection near the vessel walls. One way of improving the heat exhaust is by modifying the magnetic confinement that governs the plasma flow. In this dissertation, automated design of the magnetic configuration is pursued using adjoint based optimization methods. A simple and fast perturbation model is used to compute the magnetic field in the vacuum vessel. A stable optimal design method of the nested type is then elaborated that strictly accounts for several nonlinear design constraints and code limitations. Using appropriate cost function deffnitions, the heat is spread more uniformly over the high-heat load plasma-facing components in a practical design example. Furthermore, practical in-parts adjoint sensitivity calculations are presented that provide a way to an efficient optimization procedure. Results are elaborated for a fictituous JET (Joint European Torus) case [...] |
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| 914 | 1 | _ | |y 2017 |
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