Search Results - "EIDIETIS, N"
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Demonstration of Tokamak Discharge Shutdown with Shell Pellet Payload Impurity Dispersal
Published in Physical review letters (15-02-2019)“…The first rapid tokamak discharge shutdown using dispersive core payload deposition with shell pellets has been achieved in the DIII-D tokamak. Shell pellets…”
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2
Spatiotemporal Evolution of Runaway Electron Momentum Distributions in Tokamaks
Published in Physical review letters (22-06-2017)“…Novel spatial, temporal, and energetically resolved measurements of bremsstrahlung hard-x-ray (HXR) emission from runaway electron (RE) populations in tokamaks…”
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3
Disruptions in ITER and strategies for their control and mitigation
Published in Journal of nuclear materials (01-08-2015)“…The thermal and electromagnetic loads related to disruptions in ITER are substantial and require careful design of tokamak components to ensure they reach the…”
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4
Multiscale Chirping Modes Driven by Thermal Ions in a Plasma with Reactor-Relevant Ion Temperature
Published in Physical review letters (09-07-2021)“…A thermal ion driven bursting instability with rapid frequency chirping, considered as an Alfvénic ion temperature gradient mode, has been observed in plasmas…”
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5
Real-time plasma equilibrium reconstruction and shape control for the MAST Upgrade tokamak
Published in Nuclear fusion (01-08-2024)“…Real-time magnetic control has been developed to deliver precise control of multiple plasma shape parameters for advanced divertor configurations, including…”
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6
MHD modeling of shattered pellet injection in JET
Published in Nuclear fusion (01-06-2023)“…Nonlinear 3D MHD simulations of shattered-pellet injection (SPI) in JET show prototypical SPI-driven disruptions using the M3D-C1 and NIMROD extended-MHD…”
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7
GATM: A 3-D FE Fusion Magnet Model and Application to DIII-D and Next-generation Devices
Published in IEEE transactions on plasma science (01-02-2024)“…The General Atomics Tokamak Model (GATM) is a recently developed finite element (FE) environment for assessing the performance of tokamak magnet-plasma…”
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8
Runaway electron plateau current profile reconstruction from synchrotron imaging and Ar-II line polarization angle measurements in DIII-D
Published in Nuclear fusion (01-07-2024)“…Current profile reconstructions are obtained for high current ( I p ≃ 550 kA) post-disruption runaway electron (RE) plateau plasmas in DIII-D. Two novel…”
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9
Polarized fusion and potential in situ tests of fuel polarization survival in a tokamak plasma
Published in Nuclear fusion (01-07-2023)“…The use of spin-polarized fusion fuels would provide a significant boost towards the ignition of a burning plasma. The cross section for D + T → α + n, would…”
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10
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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11
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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12
Integrated current profile, normalized beta and NTM control in DIII-D
Published in Fusion engineering and design (01-09-2019)“…•An integrated architecture has been tested in DIII-D by using ONFR as a supervisor.•The proposed architecture enables simultaneous q-profile, beta, and NTM…”
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13
Advances and challenges in KSTAR plasma control toward long-pulse, high-performance experiments
Published in Fusion engineering and design (01-07-2020)“…An overview of advances and progress on the KSTAR plasma control improvement is given. The enhancement of the KSTAR plasma control system (PCS) continues in…”
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14
Radiation distribution for shattered pellet injection experiment with AXUV array diagnostics in KSTAR
Published in Fusion engineering and design (01-07-2022)“…•The AXUV array diagnostics for shattered pellet injection experiments in KSTAR.•The poloidal AXUV arrays (PAAs) for poloidal cross-sectional radiation…”
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15
Plasma–surface interactions during tokamak disruptions and rapid shutdowns
Published in Journal of nuclear materials (01-08-2011)“…Recent progress in understanding of disruptions and in developing methods to avoid disruption damage is presented. Nearly complete mitigation of conducted heat…”
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Journal Article Conference Proceeding -
16
New capabilities and upgrade path for the DIII-D neutral beam heating system
Published in Fusion engineering and design (01-09-2019)“…•The DIII-D neutral beam system continues to evolve to provide new capabilities.•Internal beamline components are being upgraded for higher power, longer…”
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17
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 -
18
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 -
19
TokSearch: A search engine for fusion experimental data
Published in Fusion engineering and design (01-04-2018)“…At a typical fusion research site, experimental data is stored using archive technologies that deal with each discharge as an independent set of data. These…”
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20
Achievements and lessons learned from the operation of KSTAR plasma control system upgrade
Published in Fusion engineering and design (01-05-2018)“…Results on the integration and the operation of the KSTAR plasma control system (PCS) upgrade are given. Real-time hardware, new realtime-capable operating…”
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