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dc.contributor.authorNorajitra, Prachai*
dc.date.accessioned2021-02-11T11:37:09Z
dc.date.available2021-02-11T11:37:09Z
dc.date.issued2011*
dc.date.submitted2019-07-30 20:02:00*
dc.identifier35131*
dc.identifier.issn21929963*
dc.identifier.urihttps://directory.doabooks.org/handle/20.500.12854/45317
dc.description.abstractNuclear fusion is considered as a future source of sustainable energy supply. Since the H-mode discovery in ASDEX experiment ""Divertor I"" in 1982, the divertor has been an integral part of all modern tokamaks and stellarators. The major goal of this thesis is to develop a feasible divertor design for a fusion power plant to be built after ITER. The thesis describes the approach in the conceptual development of a helium-cooled divertor and the methods of verification and validation of the design.*
dc.languageEnglish*
dc.relation.ispartofseriesSchriftenreihe des Instituts für Angewandte Materialien, Karlsruher Institut für Technologie*
dc.subjectT1-995*
dc.subject.classificationthema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issuesen_US
dc.subject.othermachining and joining tungsten*
dc.subject.otherFusion power plant*
dc.subject.otherhigh heat flux tests*
dc.subject.otherhelium impingement cooling*
dc.subject.otherhelium-cooled divertor*
dc.titleDivertor Development for a Future Fusion Power Plant*
dc.typebook
oapen.identifier.doi10.5445/KSP/1000024270*
oapen.relation.isPublishedBy68fffc18-8f7b-44fa-ac7e-0b7d7d979bd2*
oapen.relation.isbn9783866447387*
oapen.pagesVI, 136 p.*
oapen.volume1*
peerreview.review.typeFull text
peerreview.anonymityAll identities known
peerreview.reviewer.typeEditorial board member
peerreview.reviewer.typeExternal peer reviewer
peerreview.review.stagePre-publication
peerreview.open.reviewNo
peerreview.publish.responsibilityBooks or series editor
peerreview.id51a542ec-eaeb-47c2-861d-6022e981a97a
peerreview.titleDissertations in Series (Dissertationen in Schriftenreihe)


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