22 results on '"Likhanskii, V. V."'
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2. Corrosion Model for Zirconium-Niobium Alloys in Pressurized Water Reactors
3. Determination of the effective hydraulic diameter of a defect in VVER-440 RK-3 fuel-element cladding
4. Effect of alloying elements on proclivity of zirconium alloys for nodular corrosion
5. Special Features of the Distribution of Point Defects Inside Uranium Dioxide Fuel Grains with the Formation of the Rim Layer
6. Simulation of the Hydriding Failure of Fuel Elements in Water-Cooled Reactors
7. Model of the Formation and Growth of a Gas-Filled Cavity in Boron Carbide under Irradiation
8. RTOP-Code Simulation of the Radial Distribution of Heat Release and Plutonium Isotope Accumulation in High Burnup Oxide Fuel
9. Simulation of Heat Emission from Fuel Element Cladding with Rapid Energy Input
10. Theoretical Simulation of the Quasistationary Crack Growth in Zirconium Claddings in an Iodine Atmosphere under Stress
11. Simulation of “radiation sealing” of an intergrain boundary and the influence of this effect on the release of gaseous fission products from UO2
12. Models of grain-boundary cracking and diffusion growth of integrain bubbles in rapidly heated irradiated fuel
13. Critical thermal fluxes in boiling in a thin hemispherical porous bed
14. New model of equiaxial growth of uranium dioxide grains under irradiation conditions
15. Critical heat fluxes when boiling occurs in a nonuniform heat-releasing porous medium
16. Two-phase convection in a porous medium with nonuniform volume heat release
17. Dynamics of the escape of gaseous fission products from melted nuclear fuel
18. Numerical investigation of the convection of heat-emitting liquid reactor materials taking stratification into account
19. SIMULATION OF THE HYDRIDING FAILURE OF FUEL ELEMENTS IN WATER-COOLED REACTORS
20. Application of a periodic-pulse laser radiation for working of reactor materials
21. The generation of sound in the flow of an excited gas
22. Modeling of the Oxidation of Uranium Dioxide in a Steam Atmosphere
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