Search Results - "Veshchunov, M S"
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1
On the Theory of Nucleation of Ionic Salts from Aqueous Solution
Published in Journal of experimental and theoretical physics (01-06-2023)“…The theory of nucleation of ionic salts from aqueous solution is critically analyzed and further developed in two limiting cases of sparingly and highly…”
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On the Theory of Two-Dimensional Homogeneous Nucleation on Close-Packed Faces of Crystals Growing from Vapour
Published in Journal of experimental and theoretical physics (01-10-2021)“…The traditional theory of two-dimensional homogeneous nucleation on flat close-packed faces of a dislocation-free crystal growing from vapour is critically…”
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3
Development of the Reiss theory for binary homogeneous nucleation of aerosols
Published in Aerosol science and technology (01-02-2024)“…The Reiss theory for binary homogeneous nucleation in binary vapor mixtures is critically analyzed and further developed. Based on the analysis of phase space…”
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4
Extension of the Smoluchowski Theory to Transitions from Dilute to Dense Regime of Brownian Coagulation: Triple Collisions
Published in Aerosol science and technology (03-08-2014)“…In order to study the transition from dilute (controlled by binary collisions) to dense (controlled by multiple collisions) regime of coagulation of colloidal…”
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5
On the saturation of unipolar and bipolar diffusion charging of aerosols
Published in Aerosol science and technology (02-01-2021)“…Modification of the traditional unipolar charging theory by consideration of the adsorption-desorption of ions on the particle surface is considered in the…”
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6
A new model of grain growth kinetics in UO2 fuel pellets. Part 1: Grain growth kinetics controlled by grain face bubble migration
Published in Journal of nuclear materials (15-11-2005)“…A new mechanism of the lenticular grain face bubble migration which controls the bubble mobility and determines the drag force exerted on the grain boundary,…”
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7
Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel
Published in Nuclear engineering and design (01-01-2006)“…The models of the mechanistic code MFPR developed in collaboration between IBRAE (Moscow, Russia) and IRSN (Cadarache, France) are described. Exhaustive…”
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8
A new model of grain growth kinetics in UO2 fuel pellets. Part 2: Normal grain growth kinetics controlled by pore migration
Published in Journal of nuclear materials (15-11-2005)“…The grain growth model presented in Part 1 is further developed and applied to the analysis of the normal grain growth kinetics controlled by pore migration…”
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9
On the Brownian coagulation of nanosized oxide particles in ODS materials under irradiation and annealing conditions
Published in Journal of nuclear materials (15-12-2020)“…Recent experiments on ion irradiation of oxide dispersion strengthened (ODS) materials to high doses at 500 °C performed at the CEA-JANNuS-Saclay facility, in…”
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10
Application of mechanistic criteria of cladding oxide shell failure to the analysis of core degradation simulated in bundle meltdown tests
Published in Nuclear engineering and design (01-09-2008)“…In this paper, the strong influence of the clad failure criteria on the calculated scenario of bundle degradation was demonstrated on the basis of comparative…”
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11
On the theory of bipolar charging of large aerosol particles
Published in Aerosol science and technology (03-07-2018)“…The theory of bipolar charging of aerosol particles is developed for large particles (≥10 µm), taking into consideration the Coulomb field screening effect,…”
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12
Severe accident research in the core degradation area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center
Published in Nuclear engineering and design (01-11-2012)“…► ISTC supported successful nuclear safety projects between EU & Russian institutes. ► Two-tier project monitoring has proved to be very successful and…”
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13
Modeling of Zr alloy burst cladding internal oxidation and secondary hydriding under LOCA conditions
Published in Journal of nuclear materials (01-06-2015)“…The recently developed mechanistic model for Zr alloy cladding hydriding has been implemented in the single-rod SVECHA/QUENCH (S/Q) code. The mass transfer in…”
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14
Mechanisms of fission gas release from defective fuel rods to water coolant during steady-state operation of nuclear power reactors
Published in Nuclear engineering and design (01-03-2019)“…•Additional mechanisms of mass exchange in defective fuel rods are considered.•Supplementary justification of the generalized diffusion model is presented.•The…”
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15
LOCA advanced failure criteria: Implementation in the mechanistic fuel performance code and practical applications
Published in Nuclear engineering and design (01-12-2022)“…The advanced Chung-Kassner criteria for the capability of fuel rods to withstand thermal shock during LOCA reflooding and to withstand post-quench fuel…”
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16
Modelling of grain face bubbles coalescence in irradiated UO2 fuel
Published in Journal of nuclear materials (29-02-2008)“…Two different mechanisms of grain face bubbles coalescence in irradiated UO2 fuel are critically analysed and further developed. Coalescence of face bubbles…”
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17
Modelling of breakaway swelling in intermetallic fuels during low-temperature irradiation
Published in Journal of nuclear materials (01-01-2022)“…A new interpretation of the breakaway swelling observed in high-density dispersion fuels (U6Fe, U3Si, etc.) under irradiation in research reactors is proposed…”
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18
Molten corium oxidation model
Published in Nuclear engineering and design (01-11-2005)“…In order to model oxidation of Zr–O and U–Zr–O melts, post-test appearance of refrozen oxidised melts in the CORA and QUENCH bundle tests performed at the…”
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19
An advanced model for intragranular bubble diffusivity in irradiated UO2 fuel
Published in Journal of nuclear materials (31-05-2008)“…An advanced model for intragranular bubble diffusivity in irradiated UO2 fuel is developed. Three various (surface, volume and gas-phase) mechanisms for the…”
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20
Development of the MFPR/R code for characterization of the rim zone and high burnup structure evolution in UO2 fuel pellets
Published in Journal of nuclear materials (15-04-2019)“…The MFPR/R code designed for mechanistic modelling of irradiated UO2 fuel, was further developed for characterization of the rim zone and high burnup structure…”
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