69 research outputs found
Morphology of PbTe crystal surface sputtered by argon plasma under Secondary Neutral Mass Spectrometry conditions
We have investigated morphology of the lateral surfaces of PbTe crystal
samples grown from melt by the Bridgman method sputtered by Ar+ plasma with ion
energy of 50-550 eV for 5-50 minutes under Secondary Neutral Mass Spectrometry
(SNMS) conditions. The sputtered PbTe crystal surface was found to be
simultaneously both the source of sputtered material and the efficient
substrate for re-deposition of the sputtered material during the depth
profiling. During sputtering PbTe crystal surface is forming the dimple relief.
To be redeposited the sputtered Pb and Te form arrays of the microscopic
surface structures in the shapes of hillocks, pyramids, cones and others on the
PbTe crystal sputtered surface. Correlation between the density of re-deposited
microscopic surface structures, their shape, and average size, on the one hand,
and the energy and duration of sputtering, on the other, is revealed
Territorial Organization of Educational-Pedagogic Complex in the Chernivtsi Oblast
Реформування галузі освіти та культури на сучасному етапі загострює питання щодо вдосконалення структури освітньо-виховного комплексу. Основний акцент зроблено на територіальній структурі освітньо-виховного комплексу, її складниках та виокремленні перспективних елементів його функціонування.The present-day reformation of education and culture urges the development of educational-pedagogic complex structural development. The article accentuates upon the territorial structure of educational-pedagogic complex, its (structure) components and disclosure of perspective elements in the territorial structure of educational-pedagogic complex of the Chernivtsi Oblast
Interaction between Mn Ions and Free Carriers in Quantum Wells with Asymmetrical Semimagnetic Barriers
Investigations of photoluminescence (PL) in the magnetic field of quantum
structures based on the ZnSe quantum well with asymmetrical ZnBeMnSe and ZnBeSe
barriers reveal that the introduction of Be into semimagnetic ZnMnSe causes a
decrease of the exchange integrals for conductive and valence bands as well as
the forming of a complex based on Mn, degeneration of an energy level of which
with the energy levels of the V band of ZnBeMnSe or ZnSe results in spin-flip
electron transitions.Comment: Accepted to Europhys. Let
Magnetic field-induced exchange effects between Mn ions and free carriers in ZnSe quantum well through the intermediate nonmagnetic barrier studied by photoluminescence
Photoluminescence (PL) of the 50 nm / nm
/ 2.5 nm / 30 nm
structures is investigated as a function of magnetic field () and thickness
() of intermediate nonmagnetic barrier between the
semimagnetic barrier and quantum well at
the temperature 1.2 K. The rate of the shift of different PL bands of the
structures under study is estimated in low and high magnetic fields. The causes
of the shift rate increase under pass from low to high magnetic fields are
interpreted. The peculiarities of the effect of the intermediate barrier on the
luminescence properties of the structures are presented. It is shown that
deformation of adjacent layers by the barrier plays a crucial role in the
formation of these properties, especially in forming the complexes in the
layer. The change of the band gap as well as of
the donor and acceptor levels energies under the effect of biaxial compression
of the layer by the are
estimated. It is concluded that the intermediate
barrier also appreciably changes the effect of giant Zeeman splitting of the
semimagnetic barrier energy levels on the
movement of the energy levels of quantum well in a magnetic field and on
polarization of the quantum well exciton emission
Surface modification of tungsten and tungsten-tantalum alloys exposed to high-flux deuterium plasma and its impact on deuterium retention
Samples of tungsten and tungsten-tantalum alloy (with 5 mass per cent of Ta) were exposed to high-flux deuterium plasma at different fluences. The surface modification was studied with scanning electron microscopy, and deuterium retention was measured by thermal desorption spectroscopy (TDS). In the high fluence range of similar to 3.5 x 10(26)-10(27)m(-2), multiple large-size blisters are formed on the W surface, while blisters on the W-Ta surface are considerably smaller in size and number. Deuterium retention in this fluence range was found to be systematically higher in W than in W-Ta. Correlation between the evolution of the blistering patterns and the TDS spectra as a function of fluence suggests that trapping in the sub-surface cavities associated with blisters is the predominant trapping mechanism in tungsten in the case of high fluence exposures. We attribute the lower retention in W-Ta under the investigated conditions to the weaker blistering.</p
Comparative study of deuterium retention and vacancy content of self-ion irradiated tungsten
Self-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simulating microstructures generated by neutron irradiation in tungsten components of a fusion reactor. Transmission electron microscopy (TEM) has been used to characterize defects formed in tungsten samples by ion irradiation. It was found that tungsten irradiated to 0.85 dpa at relatively low temperatures develops a characteristic microstructure dominated by dislocation loops and black dots. The density and size distribution of these defects were estimated. Some of the samples exposed to self-ion irradiation were then implanted with deuterium. Thermal Desorption Spectrometry (TDS) analysis was performed to estimate the deuterium inventory as a function of irradiation damage and deuterium release as a function of temperature. Increase of inventory with increasing irradiation dose followed by slight decrease above 0.1 dpa was found. Application of Positron Annihilation Spectroscopy (PAS) to self-irradiated but not deuterium implanted samples enabled an assessment of the density of irradiation defects as a function of exposure to highenergy ions. The PAS results show that the density of defects saturates at doses in the interval from 0.085 to 0.425 displacements per atom (dpa). These results are discussed in the context of recent theoretical simulations exhibiting the saturation of defect microstructure in the high irradiation exposure limit. The saturation of damage found in PAS agrees with the simulation data described in the paper. (c) 2021 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license ( http://creativecommons.org/licenses/by-nc-nd/4.0/ )Peer reviewe
Shattered pellet injection experiments at JET in support of the ITER disruption mitigation system design
A series of experiments have been executed at JET to assess the efficacy of the newly installed shattered pellet injection (SPI) system in mitigating the effects of disruptions. Issues, important for the ITER disruption mitigation system, such as thermal load mitigation, avoidance of runaway electron (RE) formation, radiation asymmetries during thermal quench mitigation, electromagnetic load control and RE energy dissipation have been addressed over a large parameter range. The efficiency of the mitigation has been examined for the various SPI injection strategies. The paper summarises the results from these JET SPI experiments and discusses their implications for the ITER disruption mitigation scheme
Overview of JET results for optimising ITER operation
The JET 2019–2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power in 2019–2020, and tested the technical and procedural preparation for safe operation with tritium. Research along three complementary axes yielded a wealth of new results. Firstly, the JET plasma programme delivered scenarios suitable for high fusion power and alpha particle (α) physics in the coming D–T campaign (DTE2), with record sustained neutron rates, as well as plasmas for clarifying the impact of isotope mass on plasma core, edge and plasma-wall interactions, and for ITER pre-fusion power operation. The efficacy of the newly installed shattered pellet injector for mitigating disruption forces and runaway electrons was demonstrated. Secondly, research on the consequences of long-term exposure to JET-ILW plasma was completed, with emphasis on wall damage and fuel retention, and with analyses of wall materials and dust particles that will help validate assumptions and codes for design and operation of ITER and DEMO. Thirdly, the nuclear technology programme aiming to deliver maximum technological return from operations in D, T and D–T benefited from the highest D–D neutron yield in years, securing results for validating radiation transport and activation codes, and nuclear data for ITER
Overview of JET results for optimising ITER operation
The JET 2019–2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power in 2019–2020, and tested the technical and procedural preparation for safe operation with tritium. Research along three complementary axes yielded a wealth of new results. Firstly, the JET plasma programme delivered scenarios suitable for high fusion power and alpha particle (α) physics in the coming D–T campaign (DTE2), with record sustained neutron rates, as well as plasmas for clarifying the impact of isotope mass on plasma core, edge and plasma-wall interactions, and for ITER pre-fusion power operation. The efficacy of the newly installed shattered pellet injector for mitigating disruption forces and runaway electrons was demonstrated. Secondly, research on the consequences of long-term exposure to JET-ILW plasma was completed, with emphasis on wall damage and fuel retention, and with analyses of wall materials and dust particles that will help validate assumptions and codes for design and operation of ITER and DEMO. Thirdly, the nuclear technology programme aiming to deliver maximum technological return from operations in D, T and D–T benefited from the highest D–D neutron yield in years, securing results for validating radiation transport and activation codes, and nuclear data for ITER
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