А.V. Vertkov

ORCID: 0000-0001-7164-2316
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About
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Research Areas
  • Fusion materials and technologies
  • Magnetic confinement fusion research
  • Superconducting Materials and Applications
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Particle accelerators and beam dynamics
  • Advanced materials and composites
  • Plasma Diagnostics and Applications
  • Metal and Thin Film Mechanics
  • Advanced Power Generation Technologies
  • Graphite, nuclear technology, radiation studies
  • Ionosphere and magnetosphere dynamics
  • Metal Alloys Wear and Properties
  • Aluminum Alloys Composites Properties
  • Coal Combustion and Slurry Processing
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Asian Geopolitics and Ethnography
  • High Temperature Alloys and Creep
  • Copper Interconnects and Reliability
  • Nuclear Engineering Thermal-Hydraulics
  • Metallurgical Processes and Thermodynamics
  • Semiconductor materials and devices
  • Muon and positron interactions and applications
  • Characterization and Applications of Magnetic Nanoparticles
  • Vacuum and Plasma Arcs

Dollezhal Research and Development Institute of Power Engineering
2023-2025

Zvezda (Russia)
1993-2023

Russian Academy of Sciences
2018

Russian Venture Company
2018

Moscow Engineering Physics Institute
2017

Rosatom (Russia)
2009

National Agency for New Technologies, Energy and Sustainable Economic Development
2007

The ITER project development has shown that considerable difficulties are encountered when already known engineering solutions and materials used for divertor plates tokamaks of such a scale. We offer to use Li capillary-pore system (CPS) as plasma facing material tokamak divertor. Evaporated serves gas target redistributes thermal load. heat flux from the is transported first wall by radiation in periphery. This allows plate reduce flux. A solid CPS filled with liquid lithium high...

10.1088/0741-3335/44/6/322 article EN Plasma Physics and Controlled Fusion 2002-05-31

The paper is an overview of recent results Li limiter testing in T-11M tokamak. lithium based on the capillary-pore system (CPS) concept. erosion process and deuterium (D 2 ) helium (He) sorption by first wall were investigated. ability capillary forces to confine liquid CPS during disruption was demonstrated. idea combined with thin (0.6 mm) coating as a solution heat removal problem realized. As result quasi steady-state tokamak regime duration up 0.3 s clean ( Z eff = 1) plasma has been...

10.1088/0741-3335/48/6/009 article EN Plasma Physics and Controlled Fusion 2006-05-16

Lithium-based capillary porous systems (CPS) made of tungsten mesh are a part the most prospective approach to plasma facing components. Currently, as CPS is mounted directly on experimental assembly without proper joining with substrate. Tungsten filled steel could be used base structure for CPS. The experiment considers wetting by melt and features short- long-term interaction between two materials. Wetting was studied improved sessile drop experiment. results show that an average contact...

10.3897/nucet.11.139558 article EN cc-by Nuclear Energy and Technology 2025-02-14

A new functional model of the prototype closed Li circuit for protection chamber wall was tested in T-11M tokamak by simultaneous use vertical limiter as an emitter and a longitudinal its collector. Such technological scheme can be suggested steady-state fusion neutron source on basis. During plasma shots cryogenic target collected flow emitted capillary almost completely (up to 80%). These hydrogen isotopes were captured extracted outside vacuum without venting vessel which is key...

10.1088/0029-5515/55/12/123015 article EN cc-by Nuclear Fusion 2015-11-01

A short analysis of lithium properties presented in this article was carried out terms application various systems a fusion reactor. The is intended for use by the engineers and researchers involved activities on thermonuclear fusion.

10.1080/10519990802703277 article EN Plasma devices and operations 2009-02-24

This paper presents a review of the last T-11M and T-10 tokamak activity in field Li plasma facing component (PFC) investigation. Attention is mainly paid to realization concept closed loop lithium circulation as solution PFC problem steady-state DT volumetric neutron source on basis. Realization demands decision three main tasks: injection into plasma, collection before its deposition vacuum vessel return zone from collector. emitter–collector assumes that heat flux hot (limiters divertor...

10.1088/0029-5515/51/7/073044 article EN Nuclear Fusion 2011-06-22

Liquid metal infused capillary porous structures (CPSs) are considered as a potential divertor solution for DEMO due to their power handling capability and resilience long term damage. In this work the performance of such Sn-based CPS systems is assessed both experimentally via modelling. A Sn-CPS target was exposed heat fluxes up 18.1 MW m−2 in He plasma Pilot-PSI linear device. Post-mortem showed no damage nor any surface exposure underlying W-CPS felt. The small pore size (∼40 µm)...

10.1016/j.nme.2017.01.017 article EN cc-by-nc-nd Nuclear Materials and Energy 2017-03-12

Power handling experiments with a special liquid metal divertor module based on the capillary porous system technology were performed in tokamak COMPASS. The performance of two metals (Li and LiSn alloy) tested for first time under ELMy H-mode conditions. No damage mesh good exhaust capability observed both separate up to 12 MW/m2 deposited perpendicular, inter-ELM steady-state heat flux ELMs relative energy ~3% local peak fluence at ~15 kJ.m−2. droplets directly ejected from top surface...

10.1016/j.nme.2020.100801 article EN cc-by-nc-nd Nuclear Materials and Energy 2020-10-01

A short review of the modern state lithium use in experimental facilities and fusion devices is presented. This paper intended to be used by engineers researchers involved activities on thermonuclear fusion.

10.1080/10519990903172364 article EN Plasma devices and operations 2009-10-15

Two small liquid metal targets based on the capillary porous structure were exposed to divertor plasma of tokamak COMPASS. The first target was wetted by pure lithium and second one a lithium-tin alloy, both releasing mainly atoms (sputtering evaporation) when plasma. Due poorly conductive material steep surface inclination (implying surface-perpendicular heat flux 12–17 MW/m2) for 0.1–0.2 s, LiSn has reached 900 °C under ELMy H-mode. A model conduction is developed serves evaluate...

10.1016/j.nme.2020.100860 article EN cc-by-nc-nd Nuclear Materials and Energy 2020-11-30

Development of new plasma facing components (PFC) draw attention numerous scientific groups in fusion energy field. Tungsten as a main PFC material have poor machinability, thus various designs were proposed to overcome this problem. However, such technologies functional graded layers, sintering and additive are limited production size low cost-efficiency. This research considers the alternative approach steel melt injection or infiltration tungsten mesh. The results obtained establish...

10.3897/nucet.10.129596 article EN cc-by Nuclear Energy and Technology 2024-08-27

A complex of tungsten and lithium limiters is developed. It expected that application W as a plasma facing material will allow excluding carbon influx into the vacuum chamber. An additional Li limiter, arranged in shadow one, be used source. The parameters design are presented. surface limiter constructed to make use capillary-porous system (CPS). porous matrix CPS provides stability liquid under magnetohydrodinamic force effects, facilitates its constant renewal due capillary forces. shown...

10.1088/1741-4326/aa65e9 article EN Nuclear Fusion 2017-04-12

Following ELMy H-mode experiments with liquid metal divertor target on the COMPASS tokamak, we predict behavior of a similar Upgrade, where it will be exposed to surface heat fluxes even higher than those expected in future EU DEMO attached divertor.We simulate conduction, sputtering, evaporation, excitation and radiation lithium tin area.Measured high-resolution data from tokamak were rescaled towards Upgrade based many established scalings.Our simulation then yields amount released which...

10.1088/1402-4896/ac1dc9 article EN Physica Scripta 2021-08-16
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