Journal ArticleDOI
Material erosion and erosion products in disruption simulation experiments at the MK-200 UG facility
N.I. Arkhipov,V.P. Bakhtin,S.M Kurkin,V.M. Safronov,D.A. Toporkov,S.G. Vasenin,A.M. Zhitlukhin,H. Würz +7 more
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TLDR
In this paper, the authors studied the plasma/material interaction in disruption simulation experiments at the plasma gun facility MK-200 UG, where graphite, tungsten and aluminium targets (beryllium-like material) were irradiated by intense plasma streams under heat fluxes typical for international thermonuclear experimental reactor (ITER) hard disruption.About:
This article is published in Fusion Engineering and Design.The article was published on 2000-11-01. It has received 38 citations till now. The article focuses on the topics: Dense plasma focus.read more
Citations
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Journal ArticleDOI
A full tungsten divertor for ITER: Physics issues and design status
R.A. Pitts,S. Carpentier,Frederic Escourbiac,T. Hirai,V. Komarov,S.W. Lisgo,A.S. Kukushkin,A. Loarte,Mario Merola,A. Sashala Naik,R. Mitteau,Masayoshi Sugihara,B. Bazylev,P.C. Stangeby +13 more
TL;DR: In this article, the authors consider the risks engendered by the baseline divertor strategy with regard to known W plasma-material interaction issues and briefly present the current status of a possible full-tungsten (W) divertor design.
Journal ArticleDOI
Sub-ms laser pulse irradiation on tungsten target damaged by exposure to helium plasma
TL;DR: Takamura et al. as mentioned in this paper investigated the effects of a transient heat load on tungsten damaged by helium plasma irradiation using a ruby laser with long pulse duration in the divertor simulator NAGDIS-II.
Journal ArticleDOI
Experimental study of PFCs erosion under ITER-like transient loads at plasma gun facility QSPA
N. S. Klimov,V L Podkovyrov,A. Zhitlukhin,D. V. Kovalenko,B. Bazylev,G. Janeschitz,I.S. Landman,S. Pestchanyi,G. Federici,A. Loarte,Mario Merola,Jochen Linke,Takeshi Hirai,J. Compan +13 more
TL;DR: In this paper, an investigation of an erosion of the ITER-like divertor castellated targets of pure tungsten, lanthanum tengsten and CFC under plasma heat loads expected during the Type I ELMs and disruptions in ITER was carried out on a plasma gun QSPA-T at the SRC RF TRINITI under EU/RF collaboration.
Journal ArticleDOI
ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces
TL;DR: In this paper, the current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials and it is essential to perform high heat flux tests for R&D of ITER components.
Journal ArticleDOI
Application of powerful quasi-steady-state plasma accelerators for simulation of ITER transient heat loads on divertor surfaces
V. I. Tereshin,A. N. Bandura,O.V. Byrka,V.V. Chebotarev,Igor E. Garkusha,I.S. Landman,V.A. Makhlaj,I M Neklyudov,D.G. Solyakov,A.V. Tsarenko +9 more
TL;DR: In this paper, high power plasma interaction with material surfaces under conditions simulating the ITER disruptions and type I ELMs was investigated, where different materials were exposed to plasma with repetitive pulses of 250 µs duration, the ion energy of up to 0.6 keV, and the heat loads varying in the 0.5-25 MJ m−2 range.
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Journal ArticleDOI
Plasma-wall interactions in ITER
R. Parker,C. De Michelis,G. Janeschitz,Philippe Ghendrih,H. D. Pacher,C. Grisolia,Douglass E. Post,S. Chiocchio,G. Federici,P. Ladd,ITER-Joint-Central-Team,Home-Teams +11 more
TL;DR: In this paper, the status of the design of the divertor and first-wall/shield, the main in-vessel components for ITER, is reviewed, and three materials and relevant joining techniques are developed in the R&D program.
Journal ArticleDOI
Study of structure and dynamics of shielding layer for inclined incidence of plasma stream at MK-200 facility.
N.I. Arkhipov,V.P. Bakhtin,S. M. Kurkin,V.M. Safronov,D.A. Toporkov,S. G. Vasenin,H. Wuerz,A.M. Zhitlukhin +7 more
TL;DR: In this article, the first disruption simulation experiment under plasma stream power density of 30-40 MW/cm2 is presented, where POCO and RGT graphite were exposed to perpendicular and inclined incidence of hydrogen plasma stream with energy density up to 1.4 kJ/cm 2, directed ion energy of 2-3 keV in the presence of magnetic field up to 3.3 T.
Journal ArticleDOI
Plasma/Surface Interaction in ITER Tokamak Disruption Simulation Experiments
Hermann WÜrz,Nicolai Arkhipov,Vitali Bakhtin,Boris Bazylev,I.S. Landman,Valeri Safronov,Dima Toporkov,Sergej Vasenin,Anatoli Zhitlukhin +8 more
TL;DR: In this article, the lifetime of plasma-facing components for the International Thermonuclear Experimental Reactor (ITER) against nonnormal high heat loads, credit is taken from the existence of a plasma shield that protects the target from excessive evaporation.
Journal ArticleDOI
Plasma shield dynamics and target erosion in disruption simulation experiments
H. Würz,S. Pestchanyi,F. Kappler +2 more
TL;DR: In this article, the dynamics of carbon plasma shields and graphite target erosion experimentally studied at the recently upgraded plasma gun facility MK-200 UG at TRINITI Troitsk are compared with numerical results from FOREV-2 which allows a 2D modeling of hot plasma target interaction.