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Details

Autor(en) / Beteiligte
Titel
Initial DEMO tokamak design configuration studies
Ist Teil von
  • Fusion engineering and design, 2015-10, Vol.98-99, p.1423-1426
Ort / Verlag
Elsevier B.V
Erscheinungsjahr
2015
Quelle
ScienceDirect
Beschreibungen/Notizen
  • •A definition of main DEMO requirements.•A description of the DEMO tokamak design configuration.•A description of issues yet to be solved. To prepare the DEMO conceptual design phase a number of physics and engineering assessments were carried out in recent years in the frame of EFDA concluding in an initial design configuration of a DEMO tokamak. This paper gives an insight into the identified engineering requirements and constraints and describes their impact on the selection of the technologies and design principles of the main tokamak components. The EU DEMO program aims at making best use of the technologies developed for ITER (e.g., magnets, vessel, cryostat, and to some degree also the divertor). However, other systems in particular the breeding blanket require design solutions and advanced technologies that will only partially be tested in ITER. The main differences from ITER include the requirement to breed, to extract, to process and to recycle the tritium needed for plasma operation, the two orders of magnitude larger lifetime neutron fluence, the consequent radiation dose levels, which limit remote maintenance options, and the requirement to use low-activation steel for in-vessel components that also must operate at high temperature for efficient energy conversion.
Sprache
Englisch
Identifikatoren
ISSN: 0920-3796
eISSN: 1873-7196
DOI: 10.1016/j.fusengdes.2015.05.027
Titel-ID: cdi_hal_primary_oai_HAL_hal_03981235v1

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