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Overview of EU DEMO design and R&D activities

Fusion Engineering and Design, 2014
Abstract One important objective of the EU fusion roadmap Horizon 2020 is to lay the foundation of a Demonstration Fusion Power Reactor (DEMO) to follow ITER, with the capability of generating several 100 MW of net electricity to the grid and operating with a closed fuel-cycle by 2050.
Christian Bachmann, Thomas Franke
exaly   +3 more sources

Preliminary Design of DEMO PF Coils Based on EU DEMO 2018 Baseline

IEEE Transactions on Applied Superconductivity, 2020
The dimensioning of Winding Packs and allocation of materials in DEMO PF coils is proposed based on the requirements defined by the EUROfusion 2018 DEMO baseline. The coils are pancake-wound and use two types of forced flow cable-in-conduit conductors.
Mithlesh Kumar   +3 more
openaire   +1 more source

Key EU DEMO plant and building layout criteria

Fusion Engineering and Design, 2021
An early attention to the layout of both plant site and its buildings is essential in a complex plant under preliminary design as DEMO in order to meet the assigned targets, namely i) the licensing requirements ii) a good availability in delivery electricity to the grid.
S. Ciattaglia   +10 more
openaire   +3 more sources

Service Joining Strategy for the EU DEMO

Fusion Engineering and Design, 2020
As part of the European Research Roadmap to the Realisation of Fusion Energy, the DEMO reactor aims to show the feasibility of a fusion power plant. Due to the loss of revenue created by downtime and the potential for a breakdown to render a reactor inoperable, maintenance is “mission critical” for a power plant.
Tremethick, Tristan   +5 more
openaire   +1 more source

Parametric Studies of the EU DEMO Central Solenoid

IEEE Transactions on Applied Superconductivity, 2023
The Central Solenoid (CS) is at the core of the EU DEMO tokamak, and has a strong impact on the tokamak design and the overall machine size. By ramping its current, the CS generates a change of magnetic flux, which initiates the plasma, and induces and controls the plasma current.
Xabier Sarasola   +7 more
openaire   +2 more sources

Demo blanket technology R&D results in EU

Fusion Engineering and Design, 2002
Abstract The European breeding blanket R&D for DEMO is focussed on the development of two concepts: the Water Cooled Lithium Lead (WCLL) and the Helium Cooled Pebble Bed (HCPB). Test Blanket Modules (TBMs) based on these two concepts will be tested in ITER during the first 10 years of operation.
Gasparotto, M.   +4 more
openaire   +3 more sources

Safety important classification of EU DEMO components

Fusion Engineering and Design, 2019
Abstract The identification of structures, systems and components (SSCs) performing safety functions is of paramount importance for an EU DEMO development in all phases of the project: design, fabrication, commissioning, operation, maintenance, inspections and tests.
Pinna, Tonio   +3 more
openaire   +1 more source

Permeator Simulations for the EU-DEMO Fuel Cycle

Fusion Science and Technology, 2020
Palladium alloy permeators are foreseen for the retrieval of hydrogen in the fusion fuel cycle of the European DEMO power plant.
Hörstensmeyer, Yannick Nicolas   +3 more
openaire   +2 more sources

The EU DEMO Plant Electrical System: Issues and perspective

Fusion Engineering and Design, 2020
In the EU DEMOnstration power plant, the Plant Electrical System (PES) is one of the largest systems; its scope covers the electrical power generation and the Power Supply (PS) systems necessary for supplying all the plant loads. The studies conducted so far have been addressed to understand, on the one hand the specific design challenges with respect ...
E. Gaio   +8 more
openaire   +4 more sources

High temperature superconductor cables for EU-DEMO TF-magnets

Fusion Engineering and Design, 2017
Abstract Actual progress of High Temperature Superconductor (HTS) RE BCO tapes show an enormous increase of critical current density especially at highest field. These results offer new possibilities for the application of RE BCO for large fusion magnets with a magnetic field well above 13 T at the conductor and a large temperature margin > 10 K ...
Fietz, Walter H.   +3 more
openaire   +2 more sources

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