Search Results - "Hyatt, A. W."
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Achievement of Reactor-Relevant Performance in Negative Triangularity Shape in the DIII-D Tokamak
Published in Physical review letters (18-03-2019)“…Plasma discharges with a negative triangularity (δ=-0.4) shape have been created in the DIII-D tokamak with a significant normalized beta (β_{N}=2.7) and…”
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Integration of full divertor detachment with improved core confinement for tokamak fusion plasmas
Published in Nature communications (01-03-2021)“…Divertor detachment offers a promising solution to the challenge of plasma-wall interactions for steady-state operation of fusion reactors. Here, we…”
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3
Compatibility of the radiating divertor with high performance plasmas in DIII-D
Published in Journal of nuclear materials (15-06-2007)“…A radiating divertor approach was successfully applied to high performance ‘hybrid’ plasmas [M.R. Wade et al., in: Proceedings of the 20th IAEA Fusion Energy…”
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Journal Article Conference Proceeding -
4
A high-density and high-confinement tokamak plasma regime for fusion energy
Published in Nature (London) (16-05-2024)“…The tokamak approach, utilizing a toroidal magnetic field configuration to confine a hot plasma, is one of the most promising designs for developing reactors…”
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Plasma control system for “Day-One” operation of KSTAR tokamak
Published in Fusion engineering and design (01-06-2009)“…A complete plasma control system (PCS) has been developed for KSTAR’s first plasma campaign as a collaborative project with the DIII-D team. The KSTAR real…”
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Journal Article Conference Proceeding -
6
Author Correction: A high-density and high-confinement tokamak plasma regime for fusion energy
Published in Nature (London) (13-06-2024)Get full text
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7
First results examining the compatibility of RMP ELM suppression with the radiating divertor in DIII-D
Published in Journal of nuclear materials (01-08-2011)“…We report on recent DIII-D experiments that integrate edge localized mode (ELM) suppression using resonant magnetic perturbations (RMPs) with divertor heat…”
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Journal Article Conference Proceeding -
8
Migration of artificially introduced micron-size carbon dust in the DIII-D divertor
Published in Journal of nuclear materials (15-06-2007)“…Migration of pre-characterized carbon dust in a tokamak environment was studied by introduction of ∼30mg of micron-size (∼6μm median diameter) dust in the…”
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Journal Article Conference Proceeding -
9
DIII-D Integrated plasma control solutions for ITER and next-generation tokamaks
Published in Fusion engineering and design (01-04-2008)“…Plasma control design approaches and solutions developed at DIII-D to address its control-intensive advanced tokamak (AT) mission are applicable to many…”
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10
Plasma Startup Design of Fully Superconducting Tokamaks EAST and KSTAR With Implications for ITER
Published in IEEE transactions on plasma science (01-03-2010)“…Recent commissioning of two major fully superconducting (SC)-shaped tokamaks, Experimental Advanced Superconducting Tokamak (EAST) and Korean Superconducting…”
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Journal Article Conference Proceeding -
11
Plasma impurity content, gas fueling, and exhaust on DIII-D over extended periods between boronizations
Published in Journal of nuclear materials (15-06-2009)“…During the 2006 and 2007 DIII-D experimental campaigns the rate of boronization events was reduced significantly from past campaigns with no detrimental…”
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Journal Article Conference Proceeding -
12
Physics Operations With the DIII-D Plasma Control System
Published in IEEE transactions on plasma science (01-03-2010)“…The DIII-D device began operation in 1986, and a fully digital plasma control system (PCS) was implemented in 1993. Over time, the success of the PCS to…”
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Journal Article Conference Proceeding -
13
Sensitivity of injected argon behavior to changes in magnetic balance in double-null plasmas in DIII-D
Published in Journal of nuclear materials (15-06-2009)“…Recent DIII-D experiments show that both magnetic balance and particle drifts are important to understanding how argon impurities accumulate in balanced and…”
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Journal Article Conference Proceeding -
14
Heat flux management via advanced magnetic divertor configurations and divertor detachment
Published in Journal of nuclear materials (01-08-2015)“…The snowflake divertor (SFD) control and detachment control to manage the heat flux at the divertor are successfully demonstrated at DIII-D. Results of the…”
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15
Radiative snowflake divertor studies in DIII-D
Published in Journal of nuclear materials (01-08-2015)“…Recent DIII-D experiments assessed the snowflake divertor (SF) configuration in a radiative regime in H-mode discharges with D2 seeding. The SF configuration…”
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16
A Fusion Nuclear Science Facility for a fast-track path to DEMO
Published in Fusion engineering and design (01-10-2014)“…•A FNSF is needed to reduce the knowledge gaps to a fusion DEMO and accelerate progress toward fusion energy.•FNSF will test and qualify first-wall/blanket…”
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17
Mitigation of tokamak disruptions using high-pressure gas injection
Published in Physical review letters (29-07-2002)“…High-pressure gas-jet injection of neon and argon is shown to be a simple and robust method to mitigate the deleterious effects of disruptions on the DIII-D…”
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High precision strike point control to support experiments in the DIII-D small angle slot divertor
Published in Fusion engineering and design (01-11-2020)“…•Improved strike point position control at DIII-D to ±1 mm precision.•Precise control supports experiments in the small angle slot divertor at DIII-D.•Upgraded…”
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19
Tokamak operation with safety factor q95 < 2 via control of MHD stability
Published in Physical review letters (25-07-2014)“…Magnetic feedback control of the resistive-wall mode has enabled the DIII-D tokamak to access stable operation at safety factor q(95) = 1.9 in divertor plasmas…”
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Improved fast vertical control in KSTAR
Published in Fusion engineering and design (01-04-2019)“…Fast vertical control of shaped plasmas is essential for the successful realization of plasma operation near the limit of vertical control to achieve maximum…”
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