Search Results - "SOUKHANOVSKII, V"
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Electron-density-sensitive Line Ratios of Fe xiii- xvi from Laboratory Sources Compared to CHIANTI
Published in The Astrophysical journal (20-02-2018)“…We present electron-density-sensitive line ratios for Fe xiii- xvi measured in the spectral wavelength range of 200-440 and an electron density range of (1-4)…”
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2
Real-time plasma equilibrium reconstruction and shape control for the MAST Upgrade tokamak
Published in Nuclear fusion (01-08-2024)“…Abstract Real-time magnetic control has been developed to deliver precise control of multiple plasma shape parameters for advanced divertor configurations,…”
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3
Extending the low-recycling, flat temperature profile regime in the lithium tokamak experiment-β (LTX-β) with ohmic and neutral beam heating
Published in Nuclear fusion (01-05-2023)“…Abstract Recent experiments in the lithium tokamak experiment- β (LTX- β ) have extended the duration, performance, operating conditions, and diagnosis of the…”
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4
Observation of He-like Satellite Lines of the H-like Potassium K xix Emission
Published in The Astrophysical journal (20-08-2019)“…We present measurements of the H-like potassium (K xix) X-ray spectrum and its He-like (K xviii) satellite lines, which are situated in the wavelength region…”
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5
Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX
Published in Journal of nuclear materials (01-08-2011)“…We report the dependence of the lower divertor surface heat flux profiles, measured from infrared thermography and mapped magnetically to the mid-plane on loss…”
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Journal Article Conference Proceeding -
6
Spectroscopic measurement of increases in hydrogen molecular rotational temperature with plasma-facing surface temperature and due to collisional-radiative processes in tokamaks
Published in Nuclear fusion (01-09-2023)“…Abstract Spatially resolved rotational temperature of ground state hydrogen molecules desorbed from plasma-facing surface was measured in QUEST, LTX-β, and…”
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7
Enhanced energy confinement and performance in a low-recycling tokamak
Published in Physical review letters (18-08-2006)“…Extensive lithium wall coatings and liquid lithium plasma-limiting surfaces reduce recycling, with dramatic improvements in Ohmic plasma discharges in the…”
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8
Continuous improvement of H-mode discharge performance with progressively increasing lithium coatings in the National Spherical Torus Experiment
Published in Physical review letters (30-09-2011)“…Lithium wall coatings have been shown to reduce recycling, improve energy confinement, and suppress edge localized modes in the National Spherical Torus…”
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9
Improved neutral and plasma density control with increasing lithium wall coatings in the Lithium Tokamak Experiment-β (LTX-β)
Published in Nuclear materials and energy (01-06-2023)“…A comparison of three sets of Lithium Tokamak Experiment-β (LTX-β) discharges is presented, each with progressively more lithium evaporatively deposited on the…”
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10
Measurements and 2-D modeling of recycling and edge transport in discharges with lithium-coated PFCs in NSTX
Published in Journal of nuclear materials (01-08-2011)“…The application of lithium coatings on plasma facing components has been shown to profoundly affect plasma performance in the National Spherical Torus…”
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Journal Article Conference Proceeding -
11
Transition to ELM-free improved H-mode by lithium deposition on NSTX graphite divertor surfaces
Published in Journal of nuclear materials (15-06-2009)“…Lithium evaporated onto plasma facing components in the NSTX lower divertor has made dramatic improvements in discharge performance. As lithium accumulated,…”
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Journal Article Conference Proceeding -
12
Tokamak Power Exhaust with the Snowflake Divertor: Present Results and Outstanding Issues
Published in Journal of fusion energy (01-02-2016)“…A snowflake divertor magnetic configuration (Ryutov in Phys Plasmas 14(6):064502, 2007 ) with the second-order poloidal field null offers a number of possible…”
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13
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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14
Demonstration of Tokamak ohmic flux saving by transient coaxial helicity injection in the national spherical torus experiment
Published in Physical review letters (05-03-2010)“…Transient coaxial helicity injection (CHI) started discharges in the National Spherical Torus Experiment (NSTX) have attained peak currents up to 300 kA and…”
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15
Evaporated lithium surface coatings in NSTX
Published in Journal of nuclear materials (15-06-2009)“…Two lithium evaporators were used to evaporate more than 100 g of lithium on to the NSTX lower divertor region. Prior to each discharge, the evaporators were…”
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Journal Article Conference Proceeding -
16
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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17
Hydrogen retention in lithium on metallic walls from “in vacuo” analysis in LTX and implications for high-Z plasma-facing components in NSTX-U
Published in Fusion engineering and design (01-04-2017)“…The application of lithium to plasma-facing components (PFCs) has long been used as a technique for wall conditioning in magnetic confinement devices to…”
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18
Snowflake Divertor Experiments in the DIII-D, NSTX, and NSTX-U Tokamaks Aimed at the Development of the Divertor Power Exhaust Solution
Published in IEEE transactions on plasma science (01-12-2016)“…Experimental results from the National Spherical Torus Experiment (NSTX), a medium-size spherical tokamak with a compact divertor, and DIII-D, a large…”
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19
Dependence of recycling and edge profiles on lithium evaporation in high triangularity, high performance NSTX H-mode discharges
Published in Journal of nuclear materials (01-08-2015)“…In this paper, the effects of a pre-discharge lithium evaporation variation on highly shaped discharges in the National Spherical Torus Experiment (NSTX) are…”
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20
Modeling detachment physics in the NSTX snowflake divertor
Published in Journal of nuclear materials (01-08-2015)“…The snowflake divertor is a proposed technique for coping with the tokamak power exhaust problem in next-step experiments and eventually reactors, where…”
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