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Published in 2017 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2017.01.050
Abstract: Abstract This paper presents the nuclear analysis of the European DEMO baseline 2015 with HCLL blanket carried out with the TRIPOLI-4® Monte Carlo code and the JEFF-3.2 nuclear data library. The TRIPOLI-4® model was imported…
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Keywords:
blanket;
nuclear analysis;
hcll blanket;
european demo ... See more keywords
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Published in 2018 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2018.04.074
Abstract: Abstract In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA has been developing during the last ten years for different fusion reactors designs. This work describes the new AINA…
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Keywords:
code;
safety;
european demo;
demo designs ... See more keywords
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Published in 2019 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2019.04.021
Abstract: Abstract In the current pre-concept phase of the European DEMO, integration studies of the systems in the Upper Port area are being carried out. In DEMO, the Upper Port of the Vacuum Vessel is extraordinarily…
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Keywords:
port;
upper port;
configuration;
design ... See more keywords
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Published in 2019 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2019.111265
Abstract: Abstract This paper describes the contribution given by the application of the systems engineering approach to the European DEMO Breeding Blanket (BB) integration studies, focussing on the integration of Heating & Current Drive (H&CD) and…
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Keywords:
demo breeding;
systems engineering;
engineering;
integration ... See more keywords
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Published in 2020 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2020.111676
Abstract: Abstract The anticipated heat flux limit of the European DEMO first wall is ∼1−2 MW/m2. During transient and off normal events, the heat load deposited on the wall would be much larger than the steady state…
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Keywords:
heat;
demo first;
first wall;
design ... See more keywords
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Published in 2021 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2021.112430
Abstract: Abstract The integration of the feeder system in a tokamak involves complex engineering, manufacturing and logistics issues. Therefore, within the pre-conceptual design activities of the European DEMO fusion reactor, it is important to provide a…
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Keywords:
bus;
current leads;
bus bars;
design ... See more keywords
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Published in 2021 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2021.112453
Abstract: Abstract Tritium permeation from breeder material to the Water Coolant System (WCS) in Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) is one of the technological issues to be solved in the design of the…
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Keywords:
permeation;
blanket;
corrosion;
european demo ... See more keywords
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Published in 2022 at "Journal of Instrumentation"
DOI: 10.1088/1748-0221/17/04/c04001
Abstract: Interferometry is the primary density control diagnostic for large-scale fusion devices, including ITER and DEMO. In this paper we present a ray tracing simulation based on TRAVIS accounting for relativistic effects. The study shows that…
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Keywords:
based travis;
considerations european;
demo interferometer;
interferometer polarimeter ... See more keywords