Complex of lithium and tungsten limiters for 3 MW of ECR plasma heating in T-10 tokamak. Design, first results

Lyublinski, I.E.; Vertkov, А.V.; Zharkov, M. Yu.; Мирнов, С. В.; Vershkov, V.A.; Glazyuk, Ya. V.; Notkin, G.E.; Grashin, S.A.; Kislov, A. Ya.; Komov, A. T.

doi:10.1088/1741-4326/aa65e9

Cited by 20 publications

(7 citation statements)

References 11 publications

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“…Additionally a movable Li limiter based on capillary porous structure [12,20] was mounted on the upper port. The limiter was produced by joint-stock company 'Red Star'.…”

Section: Methodsmentioning

confidence: 99%

Review of recent experiments on the T-10 tokamak with all metal wall

et al. 2017

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Transition to an all-metal wall was realized on T-10 by replacement of graphite limiters with tungsten ones. Light impurity levels remained high and W accumulation in the plasma core was revealed. A movable lithium (Li) limiter was added to investigate the possibility of the limitation of tungsten and light impurity levels in plasma. For the first time, tokamak results on tungsten protection with Li were obtained in OH and ECRH regimes. After lithization the tungsten density in the core dropped more than an order of magnitude, while W influx into plasma decreased 2–4 times. Drastic drops of light impurities in plasma were observed together with improvement of energy confinement time and density limit values. Nevertheless, Li levels in plasma remained low in both OH and ECRH regimes. Li density in the core as low as 0.5% of ne was obtained. Tungsten transport in T-10 plasma was investigated and results on prevention of W accumulation with central ECRH were obtained. Effects of plasma exposure on ITER-grade tungsten plates from limiters were studied. Investigations of density fluctuation with correlation reflectometry confirmed a decrease of fluctuation amplitude on high field side. Modeling showed that this effect can be, to a great extent, explained by the non-locality of reflectometry. Toroidal correlations at a distance of 2.5 m along field lines were studied. Three-wave interaction between geodesic acoustic modes and broad-band turbulence was found by analysis of heavy ion beam probe diagnostics data. The possibility of plasma current control and the prevention of non-thermal electron beams formation at density limit disruption by means of ECR heating and the controlled operation of OH power supply system has been demonstrated. The study of plasma density decay after gas puff switch off during density ramp-up phase in OH regimes and the effect of ‘density pump out’ during ECRH showed that both effects can be explained by the assumption regarding electron transport growth upon reaching marginal pressure profile. A new type of internal transport barrier in the narrow zone near q = 1 surface has been found.

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“…Additionally a movable Li limiter based on capillary porous structure [12,20] was mounted on the upper port. The limiter was produced by joint-stock company 'Red Star'.…”

Section: Methodsmentioning

confidence: 99%

Review of recent experiments on the T-10 tokamak with all metal wall

et al. 2017

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“…Liquid lithium contained in capillary porous system [8,9,10,11] is attractive as the first wall components for a future fusion reactor, which has been demonstrated in modern fusion devices -tokamaks T-10 [12,13], Т-11М [10,14], FTU [15,16], NSTX-U [17] and stellarator TJ-II [18,19]. At the same time, due to quick reactions of lithium with impurities (oxygen, nitrogen, carbon etc.)…”

Section: Introductionmentioning

confidence: 99%

Spectroscopic characterization of composite lithium materials irradiated with high-temperature plasma

Budaev

Fedorovich

Лубенченко

et al. 2020

Heliyon

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High-temperature plasma irradiation of materials leads to significant modification of surface structure, growth of deposited composite films and surface layers with induced self-similar granularity on the scale from macroscales to nanoscale due to strong plasma-surface interaction. The aim of this study was to characterize lithium materials irradiated with high-temperature plasma in the T-10 tokamak and PLM device. The reactivity of lithium leads to reactions with impurities in the plasma and on the vessel. Post-mortem analyses by the X-ray photoemission spectroscopy and X-ray analysis have been used to identify deposits composition and morphology. Lithium carbonate composites have been detected by analysis demonstrating materials mixing and evidence of plasmainduced structure. New structures with the high specific surface area of hierarchical granular are registered. The reference industrial powder of lithium carbonate irradiated with steady-state plasma in the PLM device has acquired a new similar structure demonstrating universal influence of plasma on the structure of irradiated materials.

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“…The Li-limiter, together with lithizited elements of the chamber, create an Li influx into the discharge. Issues related to the design of the Li-CPS limiter and its operational characteristics, as well as the technological problems of using Li as the first wall material, are considered in [1,4,15,16]. The first results of experiments with a Li limiter based on a capillary-porous structure on T-10 are given in [8].…”

Section: Introductionmentioning

confidence: 99%

Study of lithium influx, radiation, transport and influence on plasma parameters in the T-10 tokamak

Krupin

Klyuchnikov

Nurgaliev

et al. 2019

Plasma Phys. Control. Fusion

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An investigation of lithium influx to plasma, radiation, transport, and its influence on plasma parameters is carried out using spectroscopy and transport modeling methods. The lithium source in the discharge of the T-10 tokamak is a moving Li-limiter based on a tungsten capillary-pore system (CPS). A strong dependence is found between the Li influx to plasma on the distance between the Li-limiter and plasma current boundary in the scrape-off layer (SOL) region. It is shown that if the Li-limiter is located on the radius of the chamber wall (r≈40 cm), lithium influx to plasma is at a low level with a value ∼2•10 18 s −1 and the Li nuclei concentration in the plasma does not exceed ∼0.5% of electron density n e with the effective charge value Z eff ≈1.2. If the Lilimiter is moved to the current radius (a L =30 cm), lithium influx to plasma reaches ∼3•10 20 s −1 , which leads to a formation of lithium plasma with the density limit of • » n 0.5 e Gw (the Greenwald density limit) with a Z eff value of ≈2.9 and ≈10% of the remaining deuteron density. In this case, the lithium radiation losses power estimated in Li-plasma is extremely low and does not exceed ≈15% of ohmic power. All obtained results are interpreted using transport models. Changing the lithization level of the chamber walls can significantly reduce the level of C, O, and W impurities and greatly affect the Z eff values. The dependencies of energy confinement times in the electron and ion components on the value of the averaged electron density are investigated in regimes with significantly varying Z eff values. The paper presents the computational analysis of the lithium radiation power at the plasma periphery and in the SOL as a function of boundary conditions, transport characteristics, and confinement times of lithium ions.

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Complex of lithium and tungsten limiters for 3 MW of ECR plasma heating in T-10 tokamak. Design, first results

Cited by 20 publications

References 11 publications

Review of recent experiments on the T-10 tokamak with all metal wall

Review of recent experiments on the T-10 tokamak with all metal wall

Spectroscopic characterization of composite lithium materials irradiated with high-temperature plasma

Study of lithium influx, radiation, transport and influence on plasma parameters in the T-10 tokamak

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