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Please use this identifier to cite or link to this item: http://arks.princeton.edu/ark:/88435/dsp01r781wj699
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dc.contributor.authorBattaglia, D.J.-
dc.contributor.authorBoyer, M.D.-
dc.contributor.authorGerhardt, S.-
dc.contributor.authorMueller, D.-
dc.contributor.authorMyers, C.E.-
dc.contributor.authorGuttenfelder, W.-
dc.contributor.authorMenard, J.E.-
dc.contributor.authorSabbagh, S.A.-
dc.contributor.authorScotti, F.-
dc.contributor.authorBedoya, F.-
dc.contributor.authorBell, R.E.-
dc.contributor.authorBerkery, J.W.-
dc.contributor.authorDiallo, A.-
dc.contributor.authorFerraro, N.-
dc.contributor.authorJaworski, M.A.-
dc.contributor.authorKaye, S.M.-
dc.contributor.authorLeBlanc, B.P.-
dc.contributor.authorOno, M.-
dc.contributor.authorPark, J.-K.-
dc.contributor.authorPodesta, M.-
dc.contributor.authorRaman, R.-
dc.contributor.authorSoukhanovskii, V.A.-
dc.date.accessioned2018-01-11T21:20:52Z-
dc.date.available2018-01-11T21:20:52Z-
dc.date.issued2018-04-
dc.identifier.urihttp://arks.princeton.edu/ark:/88435/dsp01r781wj699-
dc.description.abstractThe National Spherical Torus Experiment Upgrade (NSTX-U) will advance the physics basis required for achieving steady-state, high-beta, and high-confinement conditions in a tokamak by accessing high toroidal field (1 T) and plasma current (1.0 - 2.0 MA) in a low aspect ratio geometry (A = 1.6 - 1.8) with flexible auxiliary heating systems (12 MW NBI, 6 MW HHFW). This paper describes progress in the development of L- and H-mode discharge scenarios and the commissioning of operational tools in the first ten weeks of operation that enable the scientific mission of NSTX-U. Vacuum field calculations completed prior to operations supported the rapid development and optimization of inductive breakdown at different values of ohmic solenoid current. The toroidal magnetic field (B_T0 = 0.65 T) exceeded the maximum values achieved on NSTX and novel long-pulse L-mode discharges with regular sawtooth activity exceeded the longest pulses produced on NSTX (tpulse > 1.8s). The increased flux of the central solenoid facilitated the development of stationary L-mode discharges over a range of density and plasma current (Ip). H-mode discharges achieved similar levels of stored energy, confinement (H98y,2 > 1) and stability (beta_N/beta_N-nowall > 1) compared to NSTX discharges for Ip < 1 MA. High-performance H-mode scenarios require an L-H transition early in the Ip ramp-up phase in order to obtain low internal inductance (li) throughout the discharge, which is conducive to maintaining vertical stability at high elongation (kappa > 2.2) and achieving long periods of MHD quiescent operations. The rapid progress in developing L- and H-mode scenarios in support of the scientific program was enabled by advances in real-time plasma control, efficient error field identification and correction, effective conditioning of the graphite wall and excellent diagnostic availability.en_US
dc.description.tableofcontentsreadme, digital data filesen_US
dc.language.isoen_USen_US
dc.publisherPrinceton Plasma Physics Laboratory, Princeton Universityen_US
dc.relationNuclear Fusion vol. 58 p. 046010 (April 2018)en_US
dc.relation.isreferencedbyhttps://doi.org/10.1088/1741-4326/aaa6e0-
dc.subjectScenario developmenten_US
dc.subjectReal-time controlen_US
dc.subjectNSTX-Uen_US
dc.subjectSpherical tokamaken_US
dc.subjectWall conditioningen_US
dc.subjectTokamak startupen_US
dc.subjectError field correctionen_US
dc.subjectL-modeen_US
dc.subjectH-modeen_US
dc.titleScenario Development During Commissioning Operations on the National Spherical Torus Experiment Upgradeen_US
dc.typeDataseten_US
pu.projectgrantnumber31016 G0001 10003086 101-
pu.depositorKaye, Stanley-
dc.contributor.funderU. S. Department of Energy contract number DE-AC02-09CH11466en_US
Appears in Collections:NSTX-U

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