Search Results - "Melikhov, O. I."

Pressure Waves due to Rapid Evaporation of Water Droplet in Liquid Lead Coolant by Melikhov, Oleg I., Melikhov, Vladimir I., Iskhakov, A. S., Yakush, Sergey

“…Flash evaporation of a superheated water droplet in heavy liquid metal coolant (lead) is considered, in application to the analysis of a lead-cooled fast…”
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Study of a Thermal Detonation Wave in a Mixture of Water Droplets and Molten Lead by Melikhov, V. I., Melikhov, O. I., Bashar, S.

“…The regularities of the wave of the thermal interaction of water drops in high-temperature molten lead, i.e., a thermal-detonation wave, are studied. Due to…”
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Thermal Interaction of High-Temperature Melts with Liquids by Melikhov, V. I., Melikhov, O. I., Yakush, S. E.

“…A review of experimental and computational-theoretical works devoted to the study of the interaction of high-temperature melts with liquids, which can lead to…”
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Validation of the STEG Code against Experimental Data on Hydrodynamics of a Horizontal Steam Generator by Abdi, H., Jafari, N. Ouregani, Melikhov, V. I., Melikhov, O. I.

“…A numerical analysis of the experiments addressed to studies of hydrodynamic processes in a horizontal steam generator has been performed using the STEG (STEam…”
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Steam generator tube rupture in lead-cooled fast reactors: Estimation of impact on neighboring tubes by Iskhakov, A.S., Melikhov, V.I., Melikhov, O.I., Yakush, S.E.

“…•Models proposed for the forces acting in steam generator tube rupture accidents.•Shock and hydrodynamic impact on neighboring tubes is evaluated.•Models are…”
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Modelling of the Liquid Jet Discharge into a Liquid-Filled Space by the VOF Method by Melikhov, V. I., Melikhov, O. I., Volkov, G. Yu, Yakush, S. E., Salekh, B.

“…The penetration of a liquid jet into a space filled with another liquid for the case of large difference in density between these liquids is examined as…”
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Validation of the STEG code using experiments on Two-Phase flow across horizontal tube bundles by Liu, Shixian, Yin, Fei, Melikhov, V.I., Melikhov, O.I.

“…The results of the validation of the STEG code using the experiments on two-phase flow across horizontal tube bundles are presented. The experiments are…”
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Recommended set of interfacial drag correlations for the two-phase flow under thermal–hydraulic conditions of a horizontal steam generator by Le, T.T., Melikhov, V.I., Melikhov, O.I.

“…•Peculiarities of two-phase flows in a horizontal steam generator are considered.•A set of interfacial drag correlations is developed.•Experiments on two slice…”
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Evaluation of energy and impulse generated by superheated steam bubble collapse in subcooled water by Melikhov, V.I., Melikhov, O.I., Yakush, S.E., Le, T.C.

“…•Collapse of superheated vapor bubble in subcooled water considered.•Vapor superheat is essential for energetic collapse to occur.•At high superheats collapse…”
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Experimental and Calculated Studies of Condensation-Induced Water Hammer by Volkov, G. J., Elkin, I. V., Kapustin, A. V., Melikhov, V. I., Melikhov, O. I., Nikonov, S. M., Trubkin, O. N.

“…— Experience gained from the operation of nuclear power plants shows that emergencies or incorrect actions of the personnel may give rise to water hammer…”
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Validation of the STEG code using PGV experiments on hydrodynamics of horizontal steam generator by Le, Tung Thanh, Melikhov, V.I., Melikhov, O.I., Nerovnov, A.A., Nikonov, S.M.

“…•The PGV test facility and the main experimental results are described.•Models of interfacial drag force are analyzed in detail.•The results of the validation…”
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Investigation into Behavior of a Steam-Water Mixture Flow Through Holes in a Submerged Perforated Sheet at High Void Fractions by Melikhov, V. I., Melikhov, O. I., Nerovnov, A. A., Nikonov, S. M.

“…Processing of experimental data on the pressure difference across a submerged perforated sheet (SPS) revealed that, at sufficiently high void fractions under…”
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Hugoniot analysis of experimental data on steam explosion in stratified melt-coolant configuration by Iskhakov, A.S., Melikhov, V.I., Melikhov, O.I., Yakush, S.E., Chung, L.T.

“…•Hugoniot analysis is applied to stratified steam explosion.•Incomplete participation of melt and coolant taken into account.•Peak pressures and conversion…”
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Numerical simulation of hydrogen evolution upon interaction between zirconium melt and water by Melikhov, O. I., Melikhov, V. I., Rtishchev, N. A., Tarasov, A. E.

“…The process of hydrogen generation upon interaction between a zirconium melt and water is studied. An oxidation model for zirconium liquid droplets in a…”
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Computational-theoretical analysis of the distribution of the thermohydraulic parameters and the concentration of dissolved impurities in a PGV-1000m horizontal steam generator performed using the STEG computer code by TRUNOV, N. B, MELIKHOV, V. I, MELIKHOV, O. I, PARFENOV, Yu. V

“…The STEG computer code for performing thermohydraulic calculations is used for a three-dimensional computational analysis of the distribution of the…”
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Investigation of accident management procedures related to loss of feedwater and station blackout in PSB-VVER integral test facility by Bucalossi, A., Del Nevo, A., Moretti, F., D’Auria, F., Elkin, I.V., Melikhov, O.I.

“…► Four integral test facility experiments related to VVER-1000 reactor. ► TH response of the VVER-1000 primary system following total loss of feedwater and…”
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Computational and experimental investigations of accident regimes in standard problems on the ISB-VVÉR thermophysical stand by BLINKOV, V. N, GASHENKO, M. P, MELIKHOV, O. I, ELKIN, I. V

“…Five standard problems of investigating accidents with loss of coolant in the first loop are studied for the first time on the basis of experiments which were…”
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Effects of momentum nonequilibrium on flame propagation and extinction in the presence of inert particles by Makhviladze, G.M., Melikhov, O.I., Roberts, J.P., Sivashinsky, G.I.

“…Numerical simulations of premixed gas flame moving in the presence of inert particles are presented. This paper provides background information concerning the…”
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Validation of Advanced Computer Codes for VVER Technology : LB-LOCA Transient in PSB-VVER Facility by Del Nevo, Alessandro, Adorni, Martina, D'Auria, Francesco, Melikhov, Oleg I., Elkin, I. V., Schekoldin, V. I., Zakutaev, M. O., Zaitsev, S. I., Benčík, M.

“…The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the…”
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Development of an integrated computer code for simulating processes occurring in the containment shell of nuclear power plants with VVÉR reactors by GABARAEV, B. A, EFANOV, A. D, ZAICHIK, L. I, MELIKHOV, O. I, SOLOV'EV, S. L, SOLOV'EV, A. L

“…The results of a competition for the development and verification of a more accurate domestic integrated computer code for simulating processes occurring in…”
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