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dc.contributor.authorWhyte, Dennis G.
dc.contributor.authorLabombard, Brian
dc.contributor.authorHughes, Jerry W., Jr.
dc.contributor.authorLipschultz, Bruce
dc.contributor.authorTerry, James L.
dc.contributor.authorBrunner, Daniel Frederic
dc.contributor.authorStangeby, P. C.
dc.contributor.authorElder, D.
dc.contributor.authorLeonard, A. W.
dc.contributor.authorWatkins, J.
dc.date.accessioned2016-08-09T16:53:32Z
dc.date.available2016-08-09T16:53:32Z
dc.date.issued2013-01
dc.identifier.issn00223115
dc.identifier.urihttp://hdl.handle.net/1721.1/103873
dc.description.abstractA model is developed which constrains heat width, λr based on global power balance, momentum conservation, pedestal stability and sheath heat transmission. The model relies on measurements of the ratio of separatrix to pedestal pressure; a ratio ∼5% is found to be expected for ITER. Applying this model indicates a constraint that the allowed λr ∼ 10–30 mm for ITER if the divertor is in the high-recycling regime as expected (T < 20 eV) while a λr ∼ 1–3 mm requires a separatrix pressure approximately equal to the top pedestal pressure in violation of physical reasoning and the concept of a pedestal. A weaker constraint is applied in the model that upstream separatrix temperature simultaneously satisfies power balance. The constrained model cannot satisfy power balance with λr < 3 mm, and in order to obtain λr ∼ 5 mm requires divertor plasma temperature >100 eV, a condition which would have very negative consequences for the divertor, but has never been observed experimentally.en_US
dc.description.sponsorshipUnited States. Department of Defense (US DOE award DE-SC00-02060)en_US
dc.description.sponsorshipUnited States. Department of Defense (contract DE-FC02-99ER54512)en_US
dc.description.sponsorshipUnited States. Department of Defense (cooperative agreement DE-FC02- 04ER54698)en_US
dc.language.isoen_US
dc.publisherElsevieren_US
dc.relation.isversionofhttp://dx.doi.org/10.1016/j.jnucmat.2013.01.088en_US
dc.rightsCreative Commons Attribution-NonCommercial-NoDerivs Licenseen_US
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/4.0/en_US
dc.sourceMIT web domainen_US
dc.titleConstraining the divertor heat width in ITERen_US
dc.typeArticleen_US
dc.identifier.citationWhyte, D. G., B. LaBombard, J.W. Hughes, B. Lipschultz, J. Terry, D. Brunner, P. C. Stangeby, D. Elder, A. W. Leonard, and J. Watkins. "Constraining the divertor heat width in ITER." Journal of Nuclear Materials 438, Supplement (July 2013), pp.S435-S439.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Plasma Science and Fusion Centeren_US
dc.contributor.mitauthorWhyte, Dennis G.en_US
dc.contributor.mitauthorLabombard, Brianen_US
dc.contributor.mitauthorHughes, Jerry W., Jr.en_US
dc.contributor.mitauthorLipschultz, Bruceen_US
dc.contributor.mitauthorTerry, James L.en_US
dc.contributor.mitauthorBrunner, Daniel Fredericen_US
dc.relation.journalJournal of Nuclear Materialsen_US
dc.eprint.versionAuthor's final manuscripten_US
dc.type.urihttp://purl.org/eprint/type/JournalArticleen_US
eprint.statushttp://purl.org/eprint/status/PeerRevieweden_US
dspace.orderedauthorsWhyte, D.G.; LaBombard, B.; Hughes, J.W.; Lipschultz, B.; Terry, J.; Brunner, D.; Stangeby, P.C.; Elder, D.; Leonard, A.W.; Watkins, J.en_US
dspace.embargo.termsNen_US
dc.identifier.orcidhttps://orcid.org/0000-0002-9001-5606
dc.identifier.orcidhttps://orcid.org/0000-0002-8753-1124
dc.identifier.orcidhttps://orcid.org/0000-0002-7841-9261
mit.licensePUBLISHER_CCen_US
mit.metadata.statusComplete


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