2017
DOI: 10.1088/1741-4326/aa600a
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Overview of NSTX Upgrade initial results and modelling highlights

Abstract: The National Spherical Torus Experiment (NSTX) has undergone a major upgrade, and the NSTX Upgrade (NSTX-U) Project was completed in the summer of 2015. NSTX-U first plasma was subsequently achieved, diagnostic and control systems have been commissioned, the H-mode accessed, magnetic error fields identified and mitigated, and the first physics research campaign carried out. During ten run weeks of operation, NSTX-U surpassed NSTX record pulse-durations and toroidal fields (TF), and high-performance ~1 MA H-mod… Show more

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Cited by 54 publications
(45 citation statements)
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“…The National Spherical Torus Experiment Upgrade (NSTX-U) is a spherical tokamak with carbon-based PFC 12–14 . During the FY2016 experimental campaign, boronization was used as the main PFC conditioning technique in NSTX-U 13,15 . Boron was deposited using a DC glow of He and deuterated Trimethyl boron (d-TMB) 15 .…”
Section: Introductionmentioning
confidence: 99%
“…The National Spherical Torus Experiment Upgrade (NSTX-U) is a spherical tokamak with carbon-based PFC 12–14 . During the FY2016 experimental campaign, boronization was used as the main PFC conditioning technique in NSTX-U 13,15 . Boron was deposited using a DC glow of He and deuterated Trimethyl boron (d-TMB) 15 .…”
Section: Introductionmentioning
confidence: 99%
“…The National Spherical Torus eXperiment Upgrade facility (NSTX-U) [1], which completed its first plasma operation campaign in 2016 [2,3], aims to span between the previous class of spherical torus devices, like NSTX [4] or the megaampere spherical tokamak (MAST) [5], and future facilities planned to study plasma-material interaction [6], nuclear comp onents [7], and demonstration of fusion power production [8,9]. NSTX-U looks to build upon the results of NSTX [10] to improve the physics understanding of several key issues for future devices, including the scaling of electron transport with field and current [11][12][13][14], the physics of fast particles [15][16][17][18], and the achievement and sustainment of non-inductive, high-β scenarios [19][20][21][22][23][24].…”
Section: Introductionmentioning
confidence: 99%
“…The main UKAEA facilities existing and in development are: JET [1], the world's largest and most capable fusion facility today, capable of using tritium, is operated by the UK for exploitation as a key part of the EUROfusion roadmap to fusion electricity (). JET is a model for ITER [2] and is the best facility to mitigate risks ahead of ITER operation.MAST Upgrade [4,8], together with NSTX-U [9], are the world's largest ‘spherical’ tokamaks. MAST Upgrade has unique features focused on the exhaust issue, challenge (ii), and will be developed and exploited with EUROfusion.…”
Section: Overview Of Ukaea's Contributions To the Fusion Researchand mentioning
confidence: 99%
“…JET is a model for ITER [2] and is the best facility to mitigate risks ahead of ITER operation. -MAST Upgrade [4,8], together with NSTX-U [9], are the world's largest 'spherical' tokamaks. MAST Upgrade has unique features focused on the exhaust issue, challenge (ii), and will be developed and exploited with EUROfusion.…”
Section: Overview Of Ukaea's Contributions To the Fusion Research And Development Challengesmentioning
confidence: 99%