А. А. Писарев

ORCID: 0000-0003-0017-1478
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About
Contact & Profiles
Research Areas
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Ion-surface interactions and analysis
  • Metal and Thin Film Mechanics
  • Nuclear Physics and Applications
  • Magnetic confinement fusion research
  • Plasma Diagnostics and Applications
  • Advanced Materials Characterization Techniques
  • Nuclear materials and radiation effects
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Diamond and Carbon-based Materials Research
  • Hydrogen Storage and Materials
  • Advanced materials and composites
  • Advanced Condensed Matter Physics
  • Nuclear reactor physics and engineering
  • Mass Spectrometry Techniques and Applications
  • Semiconductor materials and devices
  • Laser-Plasma Interactions and Diagnostics
  • Graphite, nuclear technology, radiation studies
  • Cold Fusion and Nuclear Reactions
  • Plasma Applications and Diagnostics
  • Catalytic Processes in Materials Science
  • Fuel Cells and Related Materials
  • Molten salt chemistry and electrochemical processes
  • Quantum, superfluid, helium dynamics

National Research University Higher School of Economics
2022-2025

Moscow Engineering Physics Institute
2015-2024

University of Tyumen
2024

St Petersburg University
2022

Grade Medical (Czechia)
2022

Freie Universität Berlin
2022

Boreskov Institute of Catalysis
2016

Institute of Engineering Physics
2001-2013

Kurchatov Institute
2009-2013

Jožef Stefan International Postgraduate School
2013

Management of tritium inventory remains one the grand challenges in development fusion energy, and choice plasma-facing materials is a key factor for in-vessel retention. The Atomic Molecular Data Unit International Energy Agency organized Coordinated Research Project (CRP) on overall topic reactors during period 2001-2006. This dealt with hydrogenic retention ITER's – Be, C, W compounds (mixed materials) these elements as well removal techniques. results CRP are summarized this paper...

10.13182/fst54-891 article EN Fusion Science & Technology 2008-11-01

It is illustrated how an interplay between theoretical predictions and experimental measurements of binding energies or enthalpies the corresponding equilibrium positions hydrogen isotopes at defects in metals can lead to a new understanding microscopic structure observed traps. Binding vacancies bubbles voids found be strong, weaker trap tentatively associated with self-interstitials. An extremely simple picture trapping process has evolved.

10.1103/physrevlett.49.1420 article EN Physical Review Letters 1982-11-08

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,...

10.1088/0031-8949/t167/1/014051 article EN Physica Scripta 2016-01-21

10.1016/j.nimb.2016.04.038 article EN Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms 2016-05-10

Abstract To search for substances selectively acting on tumor cells, phenotypic screening in a coculture of cells with non-tumor was used the work. The compound STOCK7S-36520, cytotoxic breast MCF7' and MCF10A contains structural elements characteristic kinase inhibitors. Analysis STOCK7S-36520 its derivative STOCK7S-47016 showed that they are new multikinase highest inhibition 84% shown by against GCK kinase. Of interest is significant selectivity action some cell lines studied: index...

10.1134/s1607672924601446 article EN cc-by Doklady Biochemistry and Biophysics 2025-04-11

Nitriding of highly alloyed titanium material Ti5Al4V2Mo was performed at 500, 600,700,800, 900°C in the mixture 50±10% Ar + N2 300-450 Pa (3-4.5 mbar) for 3-4 hours. The hardness surface increased with temperature, and 900 °C it 1.7 times higher than that untreated material. decreased depth, thickness hardened layer 30-50 μm °C. phase composition is very complex, comprising various Ti phases, nitride dioxide.

10.1016/j.phpro.2015.08.322 article EN Physics Procedia 2015-01-01

Thermal desorption spectra (TDSP) reported in the literature and resulting from thermal experiments performed on tungsten samples exposed to deuterium at several fluences are analyzed using a reaction–diffusion model including up ten different types of traps. The use large number traps allows accurate fits TDSP all unique broad spectrum detrapping energy. Detrapping energies found this work good agreement with predicted by density functional theory when hydrogen atoms trapped single vacancy....

10.1088/0029-5515/55/9/093017 article EN Nuclear Fusion 2015-08-11

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...

10.1088/1402-4896/ab4068 article EN Physica Scripta 2020-01-01

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...

10.1088/0031-8949/2014/t159/014050 article EN Physica Scripta 2014-04-01

10.1016/0022-3115(94)00613-x article EN Journal of Nuclear Materials 1995-04-01
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