Influence of boronization and carbonization on ICRF-heated plasmas in ASDEX

Ryter, F.; Gehre, O.; Kurzan, B.; Noterdaeme, J.‐M.; Siller, G.; Wesner, F.; ICRH-Team,; ASDEX-Team,; NI-Team,

doi:10.1016/0920-3796(90)90090-s

Cited by 9 publications

(4 citation statements)

References 4 publications

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“…Ryter et al reported that in ASDEX tokamak plasmas the radiated power from iron increased roughly linearly as a function of ICRF input power and as a result of neutral beam injections [9]. Furthermore, a roughly linear increase in Z eff was observed as a function of ICRF input power from which a similar increase in iron density can be inferred.…”

Section: Introductionmentioning

confidence: 95%

Intrinsic molybdenum impurity density and radiative power losses with their scalings in ohmically and ICRF heated Alcator C-Mod and FTU tokamak plasmas

May¹,

Fournier²,

Goetz³

et al. 1999

Plasma Phys. Control. Fusion

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A new radiative cooling curve for molybdenum, determined from the Hebrew University, Jerusalem-Lawrence Livermore atomic code (HULLAC) has been used to estimate the radiative power losses from various ion cyclotron resonance frequency (ICRF) and ohmically heated Alcator C-Mod tokamak plasmas and ohmically heated Frascati tokamak upgrade (FTU) plasmas. This cooling curve has been found to accurately predict the radiative losses from molybdenum ions in plasma. Radiative losses from molybdenum computed by using the HULLAC cooling curve could typically account for greater than 60% of the total radiative losses as measured by bolometry in Alcator C-Mod tokamak plasmas. The molybdenum density was found to be as high as ∼10 11 particles cm −3 (n Mo /n e ∼ 0.001) in ICRF heated plasmas. Plasmas after botonization of the plasma facing surfaces had the lowest molybdenum density and radiated power of all the plasmas examined; ICRF heated plasmas had the highest. The molybdenum density and radiative power losses were found to increase roughly linearly with input ICRF power during different heating schemes in plasmas with both H-mode and L-mode confinement. Although the molybdenum densities were found to decrease with increasing electron density, the radiative power losses did not change significantly for all types of plasmas studied in Alcator C-Mod and FTU: diverted plasmas heated with ICRF and both limited and diverted plasmas heated ohmically.

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Section: Introductionmentioning

confidence: 95%

Intrinsic molybdenum impurity density and radiative power losses with their scalings in ohmically and ICRF heated Alcator C-Mod and FTU tokamak plasmas

May¹,

Fournier²,

Goetz³

et al. 1999

Plasma Phys. Control. Fusion

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“…A number of tokamak experiments have demonstrated efficient heating of ions and electrons in the plasma core using the fast magnetosonic wave in the ion cyclotron range of frequencies (ICRF) [1][2][3][4][5][6]. Recently, transitions to the H-mode regime of improved energy confinement have been achieved with ICRF heating alone [7,8].…”

Section: Introductionmentioning

confidence: 99%

Coupling of fast waves in the ion cyclotron range of frequencies to H-mode plasmas in DIII-D

et al. 1990

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Measurements of low power (≃ 1 mW) antenna loading are used to study the coupling of a compact loop antenna structure to plasmas in the divertor configuration in DIII-D heated by neutral beam injection (NBI) or electron cyclotron heating (ECH). When a transition to the H-mode regime occurs during NBI, the antenna loading resistance drops by approximately a factor of two. This coupling decrease is due to a steepening of the edge density profile near the separatrix, accompanied by a reduction in edge density in the scrape-off layer. During edge localized modes, the opposite effects occur, and the antenna coupling increases transiently. The loading measurements are compared with theoretical calculations which take into account the measured density profiles as well as the conducting side-walls of the recessed antenna housing. Absolute agreement between the theoretical and the experimental results is obtained, including the correct dependence on the density, antenna position, RF frequency and antenna geometry. The theoretical interpretation of the results is discussed, together with the technological implications for future high power experiments.

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“…Одним из методов улучшения характеристик плазмы в исследовательских термоядерных установках является широко применяемая боронизация стенок разрядной камеры (см., например, [1][2][3][4][5][6][7]). Эффект такой процедуры со временем уменьшается [8,9], что связано с эрозией и деградацией нанесённых слоёв, поэтому процедуру боронизации необходимо повторять вновь и вновь. В связи с проблемой накопления трития чрезвычайно важным является вопрос о влиянии этих плёнок на захват и удержание водорода в материалах первой стенки.…”

Section: Introductionunclassified

Structure of Films Generated in Asdex Upgrade After Boronization and Their Influence of Hydrogen Retention in Tungsten Substrate

Moshkunov¹,

Kurnaev²,

Rusinov³

et al. 2009

PAST-TF

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Методами ядерных реакций, эллипсометрии и растровой электронной микроскопии исследованы характеристики плёнок на вольфраме, полученных при боронизации стенок в токамаке ASDEX Upgrade. Также изучено их влияние на захват водорода в вольфрамовую подложку при облучении потоками дейтериевой плазмы с параметрами, близкими к ожидаемым в ИТЭР. Структура бороводородных плёнок различна для разных случаев боронизации. Метод ядерных реакций показывает, что для боронизованной мишени проникновение водорода в вольфрам затруднено даже после полного распыления плёнки бора дейтронами. Это происходит за счёт того, что бор, присутствующий в верхних слоях вольфрамовой подложки, подавляет проникновение водорода.Ключевые слова: вольфрам, захват, дейтерий, метод ядерных реакций, эллипсометрия, боронизация. Structure of boronized films was studied by nuclear reaction analysis (NRA), ellipsometry and electron microscopy. The Influence of these films on the deuterium retention in tungsten substrate was studied by nuclear reaction analysis. D irradiation was performed at plasma conditions relevant to ITER. NRA shows that boron prevents hydrogen diffusion in tungsten even when the film is completely sputtered as confirmed by ellipsometry measurements. This happens due to boron remaining in the near-surface layer of the substrate.

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Influence of boronization and carbonization on ICRF-heated plasmas in ASDEX

Cited by 9 publications

References 4 publications

Intrinsic molybdenum impurity density and radiative power losses with their scalings in ohmically and ICRF heated Alcator C-Mod and FTU tokamak plasmas

Intrinsic molybdenum impurity density and radiative power losses with their scalings in ohmically and ICRF heated Alcator C-Mod and FTU tokamak plasmas

Coupling of fast waves in the ion cyclotron range of frequencies to H-mode plasmas in DIII-D

Structure of Films Generated in Asdex Upgrade After Boronization and Their Influence of Hydrogen Retention in Tungsten Substrate

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