Search Results - "Shestak, E"

Methodology for Evaluating the Performance of a New Pulse Oximeter Model and Pulse Oximetry Algorithm in Neonates in a Clinical Trial (Exploratory Study) by Adylov, T. S., Shestak, E. V., Starkov, V. Yu

“…While evaluating a new domestically produced pulse oximeter model in clinical practice, we discovered a lack of references in Russian-language publications on…”
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Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel by Veshchunov, M.S., Ozrin, V.D., Shestak, V.E., Tarasov, V.I., Dubourg, R., Nicaise, G.

“…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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Modeling of Zr alloy burst cladding internal oxidation and secondary hydriding under LOCA conditions by Veshchunov, M.S., Shestak, V.E.

“…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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LOCA advanced failure criteria: Implementation in the mechanistic fuel performance code and practical applications by Veshchunov, M.S., Boldyrev, A.V., Shestak, V.E.

“…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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Modelling of fission gas release from irradiated UO2 fuel under high-temperature annealing conditions by Veshchunov, M.S., Shestak, V.E.

“…The new model for the vacancy field evolution in grains during annealing of irradiated fuel was developed and implemented in the MFPR code. The model simulates…”
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An advanced model for intragranular bubble diffusivity in irradiated UO2 fuel by Veshchunov, M.S., Shestak, V.E.

“…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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Development of the MFPR/R code for characterization of the rim zone and high burnup structure evolution in UO2 fuel pellets by Tarasov, V.I., Polovnikov, P.V., Shestak, V.E., Veshchunov, M.S.

“…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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Model for evolution of crystal defects in UO2 under irradiation up to high burn-ups by Veshchunov, M S, Shestak, V E

“…The model for dislocations evolution under irradiation conditions in UO2 is developed and implemented in the MFPR code. Being combined with the MFPR set of…”
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Models for hydrogen uptake and release kinetics by zirconium alloys at high temperatures by Veshchunov, M.S., Shestak, V.E.

“…► Models for hydrogen uptake kinetics by Zr in hydrogen and steam atmospheres are refined. ► A general model for hydrogen uptake in various H2/H2O/Ar mixtures…”
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Mechanistic modelling of urania fuel evolution and fission product migration during irradiation and heating by Veshchunov, M.S., Dubourg, R., Ozrin, V.D., Shestak, V.E., Tarasov, V.I.

“…The models of the mechanistic code MFPR (Module for Fission Product Release) developed by IBRAE in collaboration with IRSN are described briefly in the first…”
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Model for oxidized corium melt interactions with vessel steel by Veshchunov, M.S., Shestak, V.E., Boldyrev, A.V.

“…•The model for U-Zr-O molten pool oxidation is extended to vessel steel corrosion.•Heat and mass exchange processes between various interaction layers are…”
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Model for melt blockage (slug) relocation and physico-chemical interactions during core degradation under severe accident conditions by Veshchunov, M.S., Shestak, V.E.

“…The model describing massive melt blockage (slug) relocation and physico-chemical interactions with steam and surrounding fuel rods of a bundle is developed on…”
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A new mechanistic code SFPR for modeling of single fuel rod performance under various regimes of LWR operation by Veshchunov, MS, Boldyrev, A V, Ozrin, V D, Shestak, V E, Tarasov, VI

“…A new mechanistic code SFPR for modeling of single fuel rod behavior under various regimes of LWR reactor operation (normal and off-normal, including severe…”
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Analysis of molten pool physico-chemical interactions and interpretation of the Phebus FP tests observations by Veshchunov, M.S., Boldyrev, A.V., Shestak, V.E., Mueller, K.

“…The new 2D model for non-equilibrium U–Zr–O melt oxidation is developed on the base of the previously developed 1D model and extended to consideration of the…”
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Oxidation of B4C by steam at high temperatures: New experiments and modelling by Steinbrück, M., Veshchunov, M.S., Boldyrev, A.V., Shestak, V.E.

“…The oxidation kinetics of various types of boron carbides (pellets, powder) were investigated in the temperature range between 1073 and 1873K. Oxidation rates…”
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Fuel performance code BERKUT-U to simulate the in-pile behavior of a single oxide or nitride fuel rod for fast reactors by Boldyrev, A.V., Dolgodvorov, A.P., Dolinskiy, I.O., Ozrin, V.D., Polovnikov, P.V., Shestak, V.E., Tarasov, V.I., Zadorozhnyi, A.V.

“…This paper describes the fuel performance code BERKUT-U, which the Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN) designed as part of…”
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Designs of pulsed power cryogenic transformers by Singh, S.K., Heyne, C.J., Hackworth, D.T., Shestak, E.J., Eckels, P.W., Rogers, J.D.

“…The design of three pulsed-power cryogenic transformers for the Los Alamos National Laboratory is summarized. The design uses two-layer air core, solenoid-type…”
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A new model of hydrogen redistribution in Zr alloy claddings during waterside corrosion in a temperature gradient by Veshchunov, M.S., Shestak, V.E., Ozrin, V.D.

“…A new model for hydrogen spatial redistribution and hydride precipitation in Zr alloys during waterside corrosion extends the traditional approach, valid for…”
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Development of the advanced mechanistic fuel performance and safety code using the multi-scale approach by Veshchunov, M.S., Boldyrev, A.V., Kuznetsov, A.V., Ozrin, V.D., Seryi, M.S., Shestak, V.E., Tarasov, V.I., Norman, G.E., Kuksin, A.Yu, Pisarev, V.V., Smirnova, D.E., Starikov, S.V., Stegailov, V.V., Yanilkin, A.V.

“…The SFPR code designed for mechanistic modeling of single fuel rod behavior under various regimes of LWR reactor operation (normal and off-normal, including…”
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Experimental test and evaluation of the Nb3Sn joint and header region for the westinghouse LCP coil by Blaugher, R., Janocko, M., Eckels, P., Patterson, A., Buttyan, J., Shestak, E.

“…The Westinghouse LCP coil utilizes a supercritical helium forced-flow Nb 3 Sn cable enclosed in a stainless steel sheath. The helium flow to the conductor is…”
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