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dc.contributor.authorLabombard, Brian
dc.contributor.authorKuang, A. Q.
dc.contributor.authorGolfinopoulos, Theodore
dc.contributor.authorTerry, J.L.
dc.contributor.authorWhyte, D.G.
dc.date.accessioned2020-03-25T20:30:35Z
dc.date.available2020-03-25T20:30:35Z
dc.date.issued2019-09
dc.date.submitted2019-01
dc.identifier.issn0029-5515
dc.identifier.urihttps://hdl.handle.net/1721.1/124345
dc.description.abstractExtremely intense power exhaust channels are projected for tokamak-based fusion power reactors; a means to handle them remains to be demonstrated. Advanced divertor configurations have been proposed as potential solutions. Recent modelling of tightly baffled, long-legged divertor geometries for the divertor test tokamak concept, ADX, has shown that these concepts may access passively stable, fully detached regimes over a broad range of parameters. The question remains as to how such divertors may perform in a reactor setting. To explore this, numerical simulations are performed with UEDGE for the longlegged divertor geometry proposed for the ARC pilot plant conceptual design-a device with projected heat flux power width (λq∥) of 0.4 mm and power exhaust of 93 MW-first for a simplified Super-X divertor configuration (SXD) and then for the actual X-point target divertor (XPTD) being proposed. It is found that the SXD, combined with 0.5% fixed-fraction neon impurity concentration, can produce passively stable, detached divertor regimes for power exhausts in the range of 80-108 MW-fully accommodating ARC's power exhaust. The XPTD configuration is found to reduce the strike-point temperature by a factor of ∼10 compared to the SXD for small separations (∼1.4λ [subscript]q [subcript]∥) between main and divertor X-point magnetic flux surfaces. Even greater potential reductions are identified for reducing separations to ∼1λ [subscript]q [subscript]∥ or less. The power handling response is found to be insensitive to the level of cross-field convective or diffusive transport assumed in the divertor leg. By raising the separatrix density by a factor of 1.5, stable fully detached divertor solutions are obtained that fully accommodate the ARC exhaust power without impurity seeding. To our knowledge, this is the first time an impurity-free divertor power handling scenario has been obtained in edge modelling for a tokamak fusion power reactor with λ [subscript]q [subcript]∥ of 0.4 mm. ©2019en_US
dc.description.sponsorshipUS DoE cooperative agreement DE-SC0014264en_US
dc.description.sponsorshipEPSRC Fusion Centre for Doctoral Training (Training grant number EP/LO1663X/1)en_US
dc.description.sponsorshipDoE Contract DE-AC52-07NA27344en_US
dc.language.isoen
dc.publisherIOP Publishingen_US
dc.relation.isversionof10.1088/1741-4326/AB394Fen_US
dc.rightsCreative Commons Attribution 3.0 unported licenseen_US
dc.rights.urihttps://creativecommons.org/licenses/by/3.0/en_US
dc.sourceIOP Publishingen_US
dc.titlePerformance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concepten_US
dc.typeArticleen_US
dc.identifier.citationWigram, M.R.K., et al., "Performance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concept." Nuclear fusion 59, 10 (2019): no. 106052 doi: 10.1088/1741-4326/AB394F ©2019en_US
dc.contributor.departmentMassachusetts Institute of Technology. Plasma Science and Fusion Centeren_US
dc.relation.journalNuclear fusionen_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.updated2020-02-27T15:53:34Z
dspace.orderedauthorsM.R.K. Wigram; B. LaBombard; M.V. Umansky; A.Q. Kuang; T. Golfinopoulos; J.L. Terry; D. Brunner; M.E. Rensink; C.P. Ridgers; D.G. Whyteen_US
dspace.date.submission2020-02-27T15:53:37Z
mit.journal.volume59en_US
mit.journal.issue10en_US
mit.licensePUBLISHER_CC
mit.metadata.statusComplete


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