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Comprehensive investigation of the metal in drums of boilers at thermal power stations
Ozhigov L., Mitrofanov A., Tolstolutskaya G., Vasilenko R., Rudenko A., Ruzhytskyi V., Ribalchenko N., Shramchenko S.
Flow-Accelerated Corrosion Wear of Power-Generating Equipment: Investigations, Prediction and Prevention: Part 3. Managing the Flow-Accelerated Corrosion of Pipelines and Equipment
Tomarov G., Shipkov A., Aflitonov D.
The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 1: Basic Models
Mosunova N.
The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 2: Validation and Verification
Alipchenkov V., Boldyrev A., Veprev D., Zeigarnik Y., Kolobaeva P., Moiseenko E., Mosunova N., Seleznev E., Strizhov V., Usov E., Osipov S., Gorbunov V., Afremov D., Semchenkov A.
Experimental investigation of the impulse gas injection into liquid and the use of experimental data for verification of the HYDRA-IBRAE/LM thermohydraulic code
Lobanov P., Usov E., Butov A., Pribaturin N., Mosunova N., Strizhov V., Chukhno V., Kutlimetov A.
Experimental Simulation of Hydrodynamics and Heat Transfer in Bubble and Slug Flow Regimes in a Heavy Liquid Metal
Usov E., Lobanov P., Kutlimetov A., Kudashov I., Chukhno V., Lezhnin S., Pribaturin N., Kashinsky O., Svetonosov A., Mosunova N.
Topical Problems Associated with Reliability and Safety of Equipment at Thermal Power Stations
Grin’ E., Chernyshev V., Bochkarev V.
Flow-accelerated corrosion 2016 international conference
Tomarov G., Shipkov A.
Verification of the EUCLID/V2 Code Based on Experiments Involving Destruction of a Liquid Metal Cooled Reactor’s Core Components
Butov A., Zhdanov V., Klimonov I., Kudashov I., Kutlimetov A., Lobanov P., Mosunova N., Sorokin A., Strizhov V., Usov E., Chukhno V.
Flow-Accelerated Corrosion Wear of Power-Generating Equipment: Investigations, Prediction, and Prevention: 2. Prediction and Prevention of General and Local Flow-Accelerated Corrosion
Tomarov G., Shipkov A., Komissarova T.
Change in working characteristics of the steam turbine metal with operating time of more than 330000 hours
Gladshteyn V., Troitskiy A.
The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor
Butov A., Zhdanov V., Klimonov I., Kudashov I., Kutlimetov A., Mosunova N., Strizhov V., Sorokin A., Frolov S., Usov E., Chukhno V.
Flow-Accelerated Corrosion Wear of Power-Generating Equipment: Investigations, Prediction, and Prevention: 1. Flow-Accelerated Corrosion Processes and Regularities
Tomarov G., Shipkov A.
Experimental studies of heat exchange for sodium boiling in the fuel assembly model: Safety substantiation of a promising fast reactor
Khafizov R., Poplavskii V., Rachkov V., Sorokin A., Trufanov A., Ashurko Y., Volkov A., Ivanov E., Privezentsev V.
Long-Term High-Temperature Longevity Testing of Thermosyphons with Actual Dimensions
Balunov B., Nikitin V., Rybnikov A., Lychakov V., Shcheglov A., Starukhina K., Matyash A., Borisov A., Pugachev N.
Mechanisms Governing Fine Fragmentation of Hot Melt Immersed in Cold Water
Ivochkin Y., Zeigarnik Y., Kubrikov K.
Types and analysis of defects in welding junctions of the header to steam generator shells on power-generating units with VVER-1000
Ozhigov L., Voevodin V., Mitrofanov A., Vasilenko R.
Comparative Estimation of the Effect from Using Different Coolants in Panel-Type Radiators of Spacecrafts
Volkov N., Volkova L., Grigor’ev A., Il’mov D., Karevskii A., Mamontov Y., Mironov V., Sobolev V., Filatov N.
Experience in Reconstructing the PT-60-90 Turbine by Reconditioning Heat Treatment of the High-Pressure Cylinder Shell
Ermolaev V., Zhuchenko L., Lyubimov A., Gladshtein V., Kremer V.
Methodology and measures for preventing unacceptable flow-accelerated corrosion thinning of pipelines and equipment of NPP power generating units
Tomarov G., Shipkov A., Lovchev V., Gutsev D.
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