Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices

Мирнов, С. В.; Azizov, É. A.; Evtikhin, V.A.; Lazarev, V.B.; Lyublinski, I.E.; Vertkov, А.V.; Prokhorov, D. Yu.

doi:10.1088/0741-3335/48/6/009

Cited by 160 publications

(142 citation statements)

References 14 publications

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“…These were followed up in subsequent experiments with a liquid lithium capillary pore system at T11-M [10], FTU [11], with a liquid lithium tray in CDX-U [12] and with lithiumization of the TJ-II stellerator [13]. A new full liquid lithium thin-film wall tokamak (LTX) will begin operation in 2010 [14].…”

Section: Introductionmentioning

confidence: 99%

Deuterium retention in NSTX with lithium conditioning

Skinner

Allain

Blanchard

et al. 2011

Journal of Nuclear Materials

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Abstract:High (! 90%) deuterium retention was observed in NSTX gas balance measurements both withand without lithiumization of the carbon plasma facing components. The gas retained in ohmic discharges was measured by comparing the vessel pressure rise after a discharge to that of a gasonly pulse with the pumping valves closed. For neutral beam heated discharges the gas input and gas pumped by the NB cryopanels were tracked. The discharges were followed by outgassing of deuterium that reduced the retention. The relationship between retention and surface chemistry was explored with a new plasma-material interface probe connected to an in-vacuo surface science station that exposed four material samples to the plasma. XPS and TDS analysis showed that the binding of D atoms is fundamentally changed by lithium -in particular atoms are weakly bonded in regions near lithium atoms bound to either oxygen or the carbon matrix.

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Section: Introductionmentioning

confidence: 99%

Deuterium retention in NSTX with lithium conditioning

Skinner

Allain

Blanchard

et al. 2011

Journal of Nuclear Materials

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“…В настоящее время существуют два подхода к использованию жидких металлов в токамаке -быст-ротекущий по поверхности ВЭ поток жидкого металла [1] и статический или медленно текущий жидкий металл в матрице КПС [2][3][4][5]. Исходя из анализа достоинств и недостатков этих подходов, в России принята за основу концепция использования КПС с жидким литием [5].…”

Section: кпс с жидким литием как основа внутрикамерных элементовunclassified

EXPERIENCE IN THE DEVELOPMENT OF LIQUID METAL PLASMA FACING ELEMENTS BASED ON CAPILLARY PORE STRUCTURE FOR STEADY STATE OPERATING TOKAMAK (Оverview)

Vertkov¹,

Lyublinski²

2017

PAST-TF

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Достижение стационарного режима функционирования термоядерного реактора ведёт к необходимости развития в области конст-рукции и выбора материалов для элементов, контактирующих с плазмой. В этом смысле наиболее перспективным решением явля-ется концепция использования капиллярно-пористых систем (КПС) с жидким металлом (в первую очередь с литием), которые обеспечивают самовозобновление поверхности элементов, контактирующих с плазмой, замкнутый оборот в них продуктов корро-зии, повышение параметров плазмы и способствуют достижению постоянного режима её горения. Кроме того, проблема отвода приходящего из плазмы потока энергии высокой степени удельной плотности (20-30 МВт/м 2 ) и поддержания на приемлемом уровне температуры поверхности элементов, контактирующих с плазмой, может быть решена введением специальной системы отвода тепла. В обзоре рассматриваются опыт развития, создания и экспериментального исследования жидкометаллических КПС, базирующийся на результатах испытания моделей элементов, контактирующих с плазмой, с системами термостабилизации в ста-ционарных условиях для токамаков T-11М, Т-10, FTU и КТМ, и различные аспекты применения жидких металлов.Ключевые слова: литий, жидкий металл, капиллярно-пористая система, токамак, взаимодействие плазмы с поверхностью, активное охлаждение. Realization of steady-state operation of fusion reactor leads to the necessity of development of essentially new design and material for plasma facing elements (PFE). In this sense the most perspective solution is the concept of use of capillary-porous system (CPS) with liquid metal that provide PFE surface self-renewal, closed circulation of their corrosion products, plasma performance improvement and promote achievement of practically stationary modes of plasma burning. Furthermore, the problem of power exhaust with high specific density (20-30 МW/m 2 ) and upkeep of a comprehensible level of temperature on PFE surface can be overcame by the introduction of heat removal system into PFE design. Experience in development, creation and experimental study of CPS based models of steady-state operating lithium PFE with systems of thermal stabilization for T-11М, Т-10, FTU and КТМ and different aspects of liquid metal application are considered. EXPERIENCE IN THE DEVELOPMENT OF LIQUID METAL PLASMA FACING ELEMENTS BASED ON CAPILLARY PORE STRUCTURE FOR STEADY STATE OPERATING TOKAMAK (Оverview)AKey words: lithium, liquid metal, capillary-porous system lithium, tokamak, plasma-surface interaction, active cooling. DOI: 10.21517/0202-3822-2017-40-3-5-13 ВВЕДЕНИЕ В настоящее время установлено, что тепловой поток на внутрикамерные элементы (ВЭ) токамака не снижается с увеличением малого радиуса камеры, как надеялись ранее, и заметно возрастает с ростом мощности нагрева плазменного шнура. Это приводит к необходимости разработки новых материалов и конструкций элементов камеры, обращённых к плазме, для обеспечения работы стационарного термо-ядерного реактора, в котором тепловые потоки могут достигать десятков МВт/м 2 , а использование тра-диционных ...

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“…These were followed by experiments with a liquid Li capillary pore system at T11-M [2] and FTU [3], with a liquid Li tray in CDX-U [4] and with lithiumization of the TJ-II stellerator [5]. A new liquid Li tokamak (LTX) began operation in 2010 [6].…”

Section: Introductionmentioning

confidence: 99%

Plasma Facing Surface Composition During NSTX Li Experiments

Skinner¹,

Sullenberger²,

Koel³

et al. 2012

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Abstract:Lithium conditioned plasma facing surfaces have lowered recycling and enhanced plasma performance on many fusion devices. However, the nature of the plasma-lithium surface interaction has been obscured by the difficulty of in-tokamak surface analysis. We report laboratory studies of the chemical composition of lithium surfaces exposed to typical residual gases found in tokamaks. Solid lithium and a molybdenum alloy (TZM) coated with lithium has been examined using x-ray photoelectron spectroscopy, temperature programmed desorption, and Auger electron spectroscopy both in ultrahigh vacuum conditions and after exposure to trace gases. Lithium surfaces near room temperature were oxidized after exposure to 1-2 Langmuirs of oxygen or water vapor. The oxidation rate by carbon monoxide was four times less. Lithiated PFC surfaces in tokamaks will be oxidized in about 100 s depending on the tokamak vacuum conditions.

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Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices

Cited by 160 publications

References 14 publications

Deuterium retention in NSTX with lithium conditioning

Deuterium retention in NSTX with lithium conditioning

EXPERIENCE IN THE DEVELOPMENT OF LIQUID METAL PLASMA FACING ELEMENTS BASED ON CAPILLARY PORE STRUCTURE FOR STEADY STATE OPERATING TOKAMAK (Оverview)

Plasma Facing Surface Composition During NSTX Li Experiments

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