Isotope exchange experiments on TEXTOR and TORE SUPRA using Ion Cyclotron Wall Conditioning and Glow Discharge Conditioning

Wauters, T.; Douai, D.; Lyssoivan, A.; Philipps, V.; Brémond, S.; Freisinger, M.; Kreter, A.; Lombard, G.; Marchuk, O.; Mollard, P.; Paul, Manash Kumar; Pégouriè, B.; Reimer, H.; Sergienko, G.; Tsitrone, E.; Vervier, M.; Wassenhove, G. Van; Wünderlich, D.; Schoor, M. Van; Oost, G. Van

doi:10.1016/j.jnucmat.2010.11.072

Cited by 17 publications

(14 citation statements)

References 6 publications

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“…The modeled neutral flux is in the range of the neutral flux that was predicted from partial H 2 , HD and D 2 pressures, gas injection data and machine pumping speeds on TEXTOR, published in [39]. Also on TEXTOR the charged particle flux on a toroidal limiter blade, with a 0.5 m 2 surface, was measured.…”

Section: Textor H 2 -Icwc Dischargesmentioning

confidence: 89%

“…Also charged particles, due to their collective drifts, diffusion across the magnetic field, and transport along the field lines will interact with the walls. To describe the wall interaction in the model, the exchange of particles between wall and plasma is represented by the recycling coefficient R. From analysis of TEXTOR and TORE SUPRA mass spectroscopy data it is found that particle recycling in ICWC plasmas can be up to R ≥ 0.99 [39]. The recycling in the model is assumed to be immediate.…”

Section: Edge Conditionsmentioning

confidence: 99%

“…To optimize the conditioning efficiency it is clear that a compromise has to be sought between the high wall fluxes on one side (neutrals: high power, high pressure; ions: high power, low pressure) and the reionization probability on the other. An alternative solution is to operate the discharges in pulsed mode: ∼ 1 s discharges followed by sufficient pumping time (order of a few times the characteristic pumping time) [39]. Fig.…”

Section: Textor H 2 -Icwc Dischargesmentioning

confidence: 99%

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0D model of magnetized hydrogen–helium wall conditioning plasmas

Wauters

Lyssoivan²,

Douai

et al. 2011

Plasma Phys. Control. Fusion

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Abstract. In this paper the 0D description of magnetized toroidal hydrogen-helium RF discharges is presented. The model has been developed to obtain insight on ICRF plasma parameters, particle fluxes to the walls and the main collisional processes, which is especially relevant for the comprehension of RF wall conditioning discharges. The 0D plasma description is based on the energy and particle balance equations for 9 principal species: H, H + , H 2 , H + 2 , H + 3 , He, He + , He 2+ and e − . It takes into account (1) elementary atomic and molecular collision processes, such as excitation/radiation, ionization, dissociation, recombination, charge exchange, etc... and elastic collisions, (2) particle losses due to the finite dimensions of the plasma volume and confinement properties of the magnetic configuration, and particle recycling, (3) active pumping and gas injection, (4) RF heating of electrons (and protons) and (5) a qualitative description of plasma impurities. The model reproduces experimental plasma density dependencies on discharge pressure and coupled RF power, both for hydrogen RF discharges (n e ≈ 1 − 5 · 10 10 cm −3 ) as for helium discharges (n e ≈ 1 − 5 · 10 11 cm −3 ). The modeled wall fluxes of hydrogen discharges are in the range of what is estimated experimentally: ∼ 10 19 − 10 20 /m 2 s for H-atoms, and ∼ 10 17 − 10 18 /m 2 s for H + -ions. It is found that experimentally evidenced impurity concentrations have an important impact on the plasma parameters, and that wall desorbed particles contribute largely to the total wall flux.

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Section: Textor H 2 -Icwc Dischargesmentioning

confidence: 89%

Section: Edge Conditionsmentioning

confidence: 99%

Section: Textor H 2 -Icwc Dischargesmentioning

confidence: 99%

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0D model of magnetized hydrogen–helium wall conditioning plasmas

Wauters

Lyssoivan²,

Douai

et al. 2011

Plasma Phys. Control. Fusion

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“…Note, however, that this is not meant to imply that the concentration, although it may have a substantial impact on coupling, is a control parameter. Detailed study and information about the isotope exchange parameters are provided elsewhere [11,17] and beyond the scope of present paper. The radial line-averaged density profile, derived from the multichannel (vertical) FIR interferometer data, is similar to that obtained in TEXTOR ICWC discharges in (He + H 2 ) [18], as shown in Fig.…”

Section: Study Of Antenna-plasma Coupling During Isotope Exchange In Jetmentioning

confidence: 99%

Plasma and antenna coupling characterization in ICRF-wall conditioning experiments

Paul

Lyssoivan²,

Koch³

et al. 2012

Fusion Engineering and Design

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“…Эффективность обезгаживания увеличивается при работе короткими и м-пульсами (0,3 с -импульс, 1,5 с -пауза). На конференции ИЦРК были посвящены пять отдельных докладов [11,[14][15][16][17].…”

Section: день третийunclassified

19th INTERNATIONAL CONFERENCE ON PLASMA SURFACE INTERACTIONS IN CONTROLLED FUSION DEVICES (PSI-19) (SAN DIEGO, USA, 24—28 MAY 2010)

Kolbasov¹

2010

PAST-TF

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Приводится краткий обзор наиболее интересных, по мнению автора, обзорных и приглашённых лекций и устных докладов, прочи-танных на конференции. Они были посвящены в основном нерешённым технологическим проблемам, связанным с сооружением международного термоядерного экспериментального реактора ИТЭР: применению вольфрамовых мишеней в диверторе, локаль-ным и переменным тепловым нагрузкам на первую стенку и дивертор, возможности уменьшить удержание трития в токамаках с углеродными мишенями дивертора, подавлению срывов плазмы и локализованных периферийных мод (ЛПМ).Ключевые слова: ИТЭР, токамак, дивертор, первая стенка, вольфрам. , 24-28 MAY 2010). B.N. KOLBASOV. The author presents a brief overview of the most interesting, in his opinion, review, invited and oral presentations delivered at the conference. They were addressed mainly to unsolved technological problems connected with the construction of International Thermonuclear Experimental Reactor ITER: application of tungsten divertor targets, local and transient heat loads on the first wall and divertor, ability to decrease tritium retention in tokamaks with carbon divertor targets, suppression of plasma disruptions and edge localized modes (ELMs). 19th INTERNATIONAL CONFERENCE ON PLASMA SURFACE INTERACTIONS IN CONTROLLED FUSION DEVICES (PSI-19) (SAN DIEGO, USA

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Isotope exchange experiments on TEXTOR and TORE SUPRA using Ion Cyclotron Wall Conditioning and Glow Discharge Conditioning

Cited by 17 publications

References 6 publications

0D model of magnetized hydrogen–helium wall conditioning plasmas

0D model of magnetized hydrogen–helium wall conditioning plasmas

Plasma and antenna coupling characterization in ICRF-wall conditioning experiments

19th INTERNATIONAL CONFERENCE ON PLASMA SURFACE INTERACTIONS IN CONTROLLED FUSION DEVICES (PSI-19) (SAN DIEGO, USA, 24—28 MAY 2010)

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