12 results on '"Kharchenko, V. V."'
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2. Computational Assessment of the Shape Change of the WWER-1000 Reactor Core Baffle Considering Effects of Radiation Swelling, Radiation Creep, and Subcritical Metal Damage Via Ductile Fracture Models
3. Computational Evaluation and Analysis of Change in Shape Peculiarities of WWER-1000 Baffle Under Design and Long-Term Operation Conditions
4. Application of Refined Calculation Guidelines to the Stress-Strain State and Fracture Resistance Analysis of the NPP Primary-Circuit System Elements
5. Special Features of Computational Assessment of the Change in Shape of WWER-1000 Reactor Core Baffle in View of Irradiation-Induced Swelling
6. Peculiarities of the Fracture Strength Design of the Branch Pipe Zone of the Nuclear Reactor Vessel
7. Improving the Computational Analysis of Stress-Strain State and Fracture Resistance of Welded Joints Between Coolant Headers and PGV-1000M Steam Generator Vessel of Nuclear Power Station
8. Calculation analysis of the stress-strain state of the collector-to-nozzle weld in the steam generator under seismic loading
9. Effect of transient heating of the outer surface of a radial crack-containing ring specimen on its brittle fracture resistance
10. Numerical simulation of stress-strain state near crack tip in a compact tensile specimen
11. Determination of stress intensity factors for semielliptical surface cracks in the WWER-1000 reactor pressure vessel from the results of solving thermoelasticity boundary value problems based on the mixed mesh-projection scheme of the finite element method
12. Anisotropy Effect of the Mechanical Metal Properties on the Assessment of the Load-Carrying Ability of the Launch Vehicle Oxidant Tank.
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