Experimental Complex for High Flux-Materials Interaction Research

Gagen-Torn, V. K.; Kirillov, I.R.; Komarov, V.; Litunovsky, V. N.; Mazul, I.; Ovchinnikov, I.; Prokofjev, Y.-U. G.; Saksagansky, G.L.; Титов, В. А.

doi:10.1016/b978-0-444-82220-8.50059-5

Cited by 11 publications

(3 citation statements)

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“…Typical ITER-like ELM events deposit ∼3 MJ in 0.1-1 ms at the area of ~1 m 2 [29] with the corresponding heat flux factor of 30-300 MJ m −2 s −1/2 . The heat loads were performed by the electron beam 'Tsefey-M' facility (Efremov Institute) [48], producing e-beams with = P 195 e kW and 18 μs duration, which was enough to cause local tungsten melting. Electron beam treatment of the tungsten mock-ups resulted in melting of a surface layer, with cracks reaching a depth of 2.4 mm and in decreasing of the micro-hardness up to a depth of 4 mm.…”

Section: Investigation Of Tungsten Mock-up Tiles Interacting With Pla...mentioning

confidence: 99%

Review of Globus-M spherical tokamak results

et al. 2015

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The first experiments on noninductive current drive (CD) using lower hybrid waves in a spherical tokamak are described. Waves at 2.45 GHz were launched by a 10 waveguide grill with 120° phase shift between neighbouring waveguides. The experimental results for a novel poloidal slowing-down scheme are described. The CD efficiency is found to be somewhat larger than that predicted theoretically whilst at the same time being somewhat less than that for standard tokamak lower hybrid CD. Geodesic acoustic modes (GAM) have been discovered in Globus-M. GAMs are localized 2-3 cm inside the separatrix. The GAM frequency agrees with theory. The mode structures of plasma density and magnetic field oscillation at the GAM frequency have been studied. Fast particle confinement during neutral beam injection has been investigated and numerically simulated. Alfvén instabilities excited by fast particles were detected by a toroidal Mirnov probe array. Their excitation conditions are discussed and the dynamics of fast ion losses induced by Alfvén eigenmodes is presented. Preliminary experiments on the isotopic effect influence on global confinement in the ohmic Nuclear Fusion

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Section: Investigation Of Tungsten Mock-up Tiles Interacting With Pla...mentioning

confidence: 99%

Review of Globus-M spherical tokamak results

et al. 2015

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“…in heating phase and 20 K/min. in cooling phase) is realized by an electron beam facility, TSEFEY, 16) Efremov Institute (Russia). Because of the short brazing time, formation of brittle intermetallic zone was considerably suppressed.…”

Section: Be Materials and The Componentsmentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.

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“…To perform comprehensive testing of the divertor mock-ups two different types of heat loads need to be selected [7]. For simulation of nominal and transient regimes (q=1-20 MW/m2, 010 s) the TSEFEY, the electron beam facility operated for last 3 years is proposed.…”

Section: Facilitiesmentioning

confidence: 99%

Development of plasma facing components for ITER at Efremov Institute

Belyakov

Filatov²,

Mazul³

17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131)

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Review of the design and R&D activity related to ITER divertor components development performed in Russia during recent years is presented. The scope of the design work and the codes used in lhis analysis are briefly reviewed. Among a variety of R&D works the key issues are presented: selection and study of armour materials, development of joining technology and mock-ups manufircturing, high heat flux tests of materials and components. The experimental and technological facilities used for this work are reviewed and a number of the alternative design solutions and experimental approaches are briefly discussed as well.

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Experimental Complex for High Flux-Materials Interaction Research

Cited by 11 publications

References 1 publication

Review of Globus-M spherical tokamak results

Review of Globus-M spherical tokamak results

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

Development of plasma facing components for ITER at Efremov Institute

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