001     836773
005     20240711113559.0
024 7 _ |a 10.1088/1741-4326/57/9/092002
|2 doi
024 7 _ |a 0029-5515
|2 ISSN
024 7 _ |a 1741-4326
|2 ISSN
024 7 _ |a 2128/15134
|2 Handle
024 7 _ |a WOS:000407854600002
|2 WOS
024 7 _ |a altmetric:20925652
|2 altmetric
037 _ _ |a FZJ-2017-05824
082 _ _ |a 530
100 1 _ |a Federici, G.
|0 P:(DE-HGF)0
|b 0
|e Corresponding author
245 _ _ |a European DEMO design strategy and consequences for materials
260 _ _ |a Vienna
|c 2017
|b IAEA
336 7 _ |a article
|2 DRIVER
336 7 _ |a Output Types/Journal article
|2 DataCite
336 7 _ |a Journal Article
|b journal
|m journal
|0 PUB:(DE-HGF)16
|s 1502348842_22524
|2 PUB:(DE-HGF)
336 7 _ |a ARTICLE
|2 BibTeX
336 7 _ |a JOURNAL_ARTICLE
|2 ORCID
336 7 _ |a Journal Article
|0 0
|2 EndNote
520 _ _ |a Demonstrating the production of net electricity and operating with a closed fuel-cycle remain unarguably the crucial steps towards the exploitation of fusion power. These are the aims of a demonstration fusion reactor (DEMO) proposed to be built after ITER. This paper briefly describes the DEMO design options that are being considered in Europe for the current conceptual design studies as part of the Roadmap to Fusion Electricity Horizon 2020. These are not intended to represent fixed and exclusive design choices but rather 'proxies' of possible plant design options to be used to identify generic design/material issues that need to be resolved in future fusion reactor systems. The materials nuclear design requirements and the effects of radiation damage are briefly analysed with emphasis on a pulsed 'low extrapolation' system, which is being used for the initial design integration studies, based as far as possible on mature technologies and reliable regimes of operation (to be extrapolated from the ITER experience), and on the use of materials suitable for the expected level of neutron fluence. The main technical issues arising from the plasma and nuclear loads and the effects of radiation damage particularly on the structural and heat sink materials of the vessel and in-vessel components are critically discussed. The need to establish realistic target performance and a development schedule for near-term electricity production tends to favour more conservative technology choices. The readiness of the technical (physics and technology) assumptions that are being made is expected to be an important factor for the selection of the technical features of the device.
536 _ _ |a 174 - Plasma-Wall-Interaction (POF3-174)
|0 G:(DE-HGF)POF3-174
|c POF3-174
|f POF III
|x 0
588 _ _ |a Dataset connected to CrossRef
700 1 _ |a Biel, W.
|0 P:(DE-Juel1)129967
|b 1
700 1 _ |a Gilbert, M. R.
|0 P:(DE-HGF)0
|b 2
700 1 _ |a Kemp, R.
|0 P:(DE-HGF)0
|b 3
700 1 _ |a Taylor, N.
|0 P:(DE-HGF)0
|b 4
700 1 _ |a Wenninger, R.
|0 P:(DE-HGF)0
|b 5
773 _ _ |a 10.1088/1741-4326/57/9/092002
|g Vol. 57, no. 9, p. 092002 -
|0 PERI:(DE-600)2037980-8
|n 9
|p 092002 -
|t Nuclear fusion
|v 57
|y 2017
|x 1741-4326
856 4 _ |y OpenAccess
|u https://juser.fz-juelich.de/record/836773/files/Federici_2017_Nucl._Fusion_57_092002.pdf
856 4 _ |y OpenAccess
|x pdfa
|u https://juser.fz-juelich.de/record/836773/files/Federici_2017_Nucl._Fusion_57_092002.pdf?subformat=pdfa
909 C O |o oai:juser.fz-juelich.de:836773
|p openaire
|p open_access
|p driver
|p VDB
|p dnbdelivery
910 1 _ |a Forschungszentrum Jülich
|0 I:(DE-588b)5008462-8
|k FZJ
|b 1
|6 P:(DE-Juel1)129967
913 1 _ |a DE-HGF
|l Kernfusion
|1 G:(DE-HGF)POF3-170
|0 G:(DE-HGF)POF3-174
|2 G:(DE-HGF)POF3-100
|v Plasma-Wall-Interaction
|x 0
|4 G:(DE-HGF)POF
|3 G:(DE-HGF)POF3
|b Energie
914 1 _ |y 2017
915 _ _ |a Creative Commons Attribution CC BY 3.0
|0 LIC:(DE-HGF)CCBY3
|2 HGFVOC
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0200
|2 StatID
|b SCOPUS
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0600
|2 StatID
|b Ebsco Academic Search
915 _ _ |a JCR
|0 StatID:(DE-HGF)0100
|2 StatID
|b NUCL FUSION : 2015
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0150
|2 StatID
|b Web of Science Core Collection
915 _ _ |a WoS
|0 StatID:(DE-HGF)0110
|2 StatID
|b Science Citation Index
915 _ _ |a WoS
|0 StatID:(DE-HGF)0111
|2 StatID
|b Science Citation Index Expanded
915 _ _ |a IF < 5
|0 StatID:(DE-HGF)9900
|2 StatID
915 _ _ |a OpenAccess
|0 StatID:(DE-HGF)0510
|2 StatID
915 _ _ |a Peer Review
|0 StatID:(DE-HGF)0030
|2 StatID
|b ASC
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)1150
|2 StatID
|b Current Contents - Physical, Chemical and Earth Sciences
915 _ _ |a National-Konsortium
|0 StatID:(DE-HGF)0430
|2 StatID
915 _ _ |a Nationallizenz
|0 StatID:(DE-HGF)0420
|2 StatID
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0199
|2 StatID
|b Thomson Reuters Master Journal List
920 1 _ |0 I:(DE-Juel1)IEK-4-20101013
|k IEK-4
|l Plasmaphysik
|x 0
980 1 _ |a FullTexts
980 _ _ |a journal
980 _ _ |a VDB
980 _ _ |a UNRESTRICTED
980 _ _ |a I:(DE-Juel1)IEK-4-20101013
981 _ _ |a I:(DE-Juel1)IFN-1-20101013


LibraryCollectionCLSMajorCLSMinorLanguageAuthor
Marc 21