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dc.contributor.authorUmansky, M.V.
dc.contributor.authorRensink, M.E.
dc.contributor.authorRognlien, T.D.
dc.contributor.authorLabombard, Brian
dc.contributor.authorBrunner, Daniel Frederic
dc.contributor.authorTerry, James L
dc.contributor.authorWhyte, Dennis G
dc.date.accessioned2018-07-25T17:43:46Z
dc.date.available2018-07-25T17:43:46Z
dc.date.issued2017-04
dc.date.submitted2017-02
dc.identifier.issn2352-1791
dc.identifier.urihttp://hdl.handle.net/1721.1/117118
dc.description.abstractA study of long-legged tokamak divertor configurations is performed with the edge transport code UEDGE (Rognlien et al., J. Nucl. Mater. 196, 347, 1992). The model parameters are based on the ADX tokamak concept design (LaBombard et al., Nucl. Fusion 55, 053020, 2015). Several long-legged divertor configurations are considered, in particular the X-point target configuration proposed for ADX, and compared with a standard divertor. For otherwise identical conditions, a scan of the input power from the core plasma is performed. It is found that as the power is reduced to a threshold value, the plasma in the outer leg transitions to a fully detached state which defines the upper limit on the power for detached divertor operation. Reducing the power further results in the detachment front shifting upstream but remaining stable. At low power the detachment front eventually moves to the primary X-point, which is usually associated with degradation of the core plasma, and this defines the lower limit on the power for the detached divertor operation. For the studied parameters, the operation window for a detached divertor in the standard divertor configuration is very small, or even non-existent; under the same conditions for long-legged divertors the detached operation window is quite large, in particular for the X-point target configuration, allowing a factor of 5–10 variation in the input power. These modeling results point to possibility of stable fully detached divertor operation for a tokamak with extended divertor legs.en_US
dc.description.sponsorshipUnited States. Department of Energy (Contract DE-AC52-07NA27344)en_US
dc.publisherElsevier BVen_US
dc.relation.isversionofhttp://dx.doi.org/10.1016/J.NME.2017.03.015en_US
dc.rightsCreative Commons Attribution-NonCommercial-NoDerivs Licenseen_US
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/4.0/en_US
dc.sourceElsevieren_US
dc.titleAssessment of X-point target divertor configuration for power handling and detachment front controlen_US
dc.typeArticleen_US
dc.identifier.citationUmansky, M.V. et al. “Assessment of X-Point Target Divertor Configuration for Power Handling and Detachment Front Control.” Nuclear Materials and Energy 12 (August 2017): 918–923 © 2017 The Authorsen_US
dc.contributor.departmentMassachusetts Institute of Technology. Plasma Science and Fusion Centeren_US
dc.contributor.mitauthorLabombard, Brian
dc.contributor.mitauthorBrunner, Daniel Frederic
dc.contributor.mitauthorTerry, James L
dc.contributor.mitauthorWhyte, Dennis G
dc.relation.journalNuclear Materials and Energyen_US
dc.eprint.versionFinal published versionen_US
dc.type.urihttp://purl.org/eprint/type/JournalArticleen_US
eprint.statushttp://purl.org/eprint/status/PeerRevieweden_US
dc.date.updated2018-07-20T18:17:08Z
dspace.orderedauthorsUmansky, M.V.; Rensink, M.E.; Rognlien, T.D.; LaBombard, B.; Brunner, D.; Terry, J.L.; Whyte, D.G.en_US
dspace.embargo.termsNen_US
dc.identifier.orcidhttps://orcid.org/0000-0002-7841-9261
dc.identifier.orcidhttps://orcid.org/0000-0002-8753-1124
dc.identifier.orcidhttps://orcid.org/0000-0002-9001-5606
mit.licensePUBLISHER_CCen_US


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