A5061425334- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Ion-surface interactions and analysis
- Metal and Thin Film Mechanics
- Nuclear Physics and Applications
- Laser-Plasma Interactions and Diagnostics
- Advanced Materials Characterization Techniques
- Advanced materials and composites
- Nuclear reactor physics and engineering
- Laser-induced spectroscopy and plasma
- Hydrogen embrittlement and corrosion behaviors in metals
- Hydrogen Storage and Materials
- Semiconductor materials and devices
- Nuclear materials and radiation effects
- Graphite, nuclear technology, radiation studies
- Diamond and Carbon-based Materials Research
- Superconducting Materials and Applications
- Cold Fusion and Nuclear Reactions
- Plasma Diagnostics and Applications
- Atomic and Molecular Physics
- Muon and positron interactions and applications
- Welding Techniques and Residual Stresses
- X-ray Spectroscopy and Fluorescence Analysis
- Analytical Chemistry and Sensors
Moscow Engineering Physics Institute
2015-2024
Plasma (Russia)
2021-2023
Max Planck Institute for Plasma Physics
2009-2016
Max Planck Society
2009-2016
Japan External Trade Organization
2014-2015
Troitsk Institute for Innovation and Fusion Research
2014
Institute of Linguistics
2011
Institute of Engineering Physics
2009
Abstract Since the publication of review Progress in ITER Physics Basis (PIPB) 2007, significant progress has been made understanding processes at plasma-material interface. This review, part ITPA Nuclear Fusion Special Issue On Path to Burning Plasma Operation , presents these developments, focusing on key areas such as physics plasma exhaust, interactions, and properties plasma-facing materials their evolution under exposure. The coordinated efforts Topical Group Scrape-Off Layer Divertor...
Erosion and deposition were studied in the JET divertor during first ITER-like wall campaign 2011 to 2012 using marker tiles. An almost complete poloidal section consisting of tiles 0, 1, 3, 4, 6, 7, 8 was studied. The data from tile surfaces completed by analysis samples remote areas inner cladding. total mass material deposited decreased a factor 4–9 compared carbon all-carbon operation before 2010. Deposits consist mainly beryllium with 5–20 at.% oxygen, respectively, small amounts Ni,...
Abstract The International Symposium on Liquid Metals Applications for Fusion (ISLA) aims to assemble scientists and engineers engaged in research lithium liquid metal applications fusion devices, facilitating discussions recent advancements challenges an open forum support the development of viable reactors. 8th (ISLA-8) was organized by Institute Plasma Physics, Chinese Academy Sciences, form September 8-12, 2024, Hefei, China. symposium attended over 70 participants, marking one highest...
Abstract The concentration of helium in tungsten fuzz-like nanostructures has been measured by means thermal desorption spectroscopy. Fuzz was formed on the W surface under intensive plasma irradiation at 1500 K. content first as-irradiated sample, and then a similar sample with fuzz mechanically scraped from surface. difference gave He fuzz, which estimated to be He/ = (13 ± 4)%.
Erosion of plasma-facing materials and successive transport redeposition eroded material are crucial processes determining the lifetime components trapped tritium inventory in redeposited layers. deposition JET divertor were studied during second ITER-like wall campaign ILW-2 2013–2014 by using a poloidal row specially prepared marker tiles including tungsten bulk tile 5. The analyzed elastic backscattering with 3–4.5 MeV incident protons nuclear reaction analysis 0.8–4.5 3He ions before...
An interaction of deuterium plasma with seeding species a material is, in particular, an issue for medium- and high-Z plasma-facing materials fusion devices to reduce the power load front surfaces. In this paper, we investigated influence nitrogen (N) into on accumulation (D) tungsten (W). Tungsten samples were exposed pure N-seeded plasmas generated by electron-cyclotron resonance source PLAQ (Plasma Quelle) experiment. D N retention each sample was subsequently analysed nuclear reaction...
The manuscript presents an overview of the erosion and deposition data in inner outer JET divertor observed during first three ITER-like wall campaigns (JET-ILW1, JET-ILW2, JET-ILW3). Erosion were studied using core samples cut out from tiles. For a similar general pattern was all campaigns: More than 60% total occurred upper region on tiles 0 1, where Be transported deposited scrape-off layer. High only tile 5. In JET-ILW2 3, together with high power fluxes at bottom 7. Additionally, peaks...
Deuterium retention in toughened, fine-grained, recrystallized tungsten-based materials doped either with titanium carbide or tantalum was investigated. Samples were irradiated by 200 eV D−1 ions to fluences the range 1 × 1022–1 1024 D m−2 at a temperature of about 310 K 38 6 1022–6 temperatures 300 and 600 K. The deuterium inventory samples examined nuclear reaction analysis thermal desorption spectroscopy (TDS). At low irradiation temperatures, both comparable pure tungsten (both...
In this paper, reduced-activation ferritic/martensitic (RAFM) steels including Eurofer (9Cr) and oxide dispersion strengthening (ODS) by the addition of Y2O3 particles with different amounts Cr, namely, (9-16)Cr were exposed to low energy deuterium (D) plasma (~20–200 eV per D) up a fluence 2.9 × 1025 D m−2 in temperature range from 290 K 700 K. The depth profile was measured 8 µm nuclear reaction analysis (NRA) total retained amount those materials determined thermal desorption spectroscopy...
The reduced-activation ferritic/martensitic (RAFM) steels including Eurofer (9Cr) and oxide dispersion strengthened (ODS) by the addition of Y2O3 particles investigated in Part I were pre-damaged either with 20 MeV W ions at room temperature IPP (Garching) or high heat flux FZJ (Juelich) subsequently exposed to low energy (~20–200 eV per D) deuterium (D) plasma up a fluence 2.9 × 1025 D m−2 range from 290 K 700 K. pre-irradiation 1 displacement atom (dpa) has no noticeable influence on steel...
Helium (He) is a product of deuterium-tritium (DT)-fusion reaction and will be natural impurity in DT plasma future fusion devices. He retention tungsten irradiated by mass-separated ions wide temperature range (300–1200 K) was investigated means thermal desorption spectroscopy (TDS). did not exceed the level 1.5 × 1021 m−2 for all samples. A significant effect air exposure on TDS spectra demonstrated. In contrast to situ measurements, release after interaction with started from ∼400 K, even...