68 results on '"Kharchenko, V. V."'
Search Results
2. Equipment and Methodology for Studying the Behavior of High-Strength Steels Under Static Pressing of Plate Specimens
3. Deformation and Failure of Thin-Sheet Specimens Made of High-Strength Steel Armox 500T Under Static and Dynamic Punching
4. Fracture Energy Characteristics of High-Strength Steels Penetrated with Armor-Piercing Strikers at Velocities Up to 1000 m/s
5. 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
6. Fracture Energy Characteristics of High-Strength Steels Hardox 450 and Armox 500T Under Impact Bending
7. Determination of Hardness of High-Strength Steels by Brinell Method. Part 2. Improvement of the Method and Measurement Results
8. Instrumentation of a Pendulum Impact Testing Machine for Impact Bending Tests
9. Determination of Fracture Energy Characteristics and Their Anisotropy for 15Kh2NMFA Steel in Impact Bending Tests
10. Determination of Hardness of High-Strength Steels by the Brinell Method. Part 1. Improvement of Measurement Accuracy
11. Application of Refined Calculation Guidelines to the Stress-Strain State and Fracture Resistance Analysis of the NPP Primary-Circuit System Elements
12. Computational Evaluation and Analysis of Change in Shape Peculiarities of WWER-1000 Baffle Under Design and Long-Term Operation Conditions
13. Wear-Resistant TiCN-Based Ceramic Materials for High-Load Friction Units
14. Anisotropy Effect of the Mechanical Metal Properties on the Assessment of the Load-Carrying Ability of the Launch Vehicle Oxidant Tank
15. Strength Assessment of Welded Joints of High-Strength Alloy Steels by Indentation Method
16. Special Features of Computational Assessment of the Change in Shape of WWER-1000 Reactor Core Baffle in View of Irradiation-Induced Swelling
17. Determination of the Mechanical Characteristics of the Metal of the Equipment of Nuclear Power Stations from Hardness Measurement and Indentation Data
18. A Setup for Complex Investigation of Mechanical Characteristics of Structural Materials for NPP Equipment
19. Peculiarities of the Fracture Strength Design of the Branch Pipe Zone of the Nuclear Reactor Vessel
20. Determination of the Temperature Dependences of the Fracture Energy Components of Specimens of Various Types in Impact Bending Tests
21. 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
22. Computation Software for Strength and Elastic Characteristics of Polymer Composites
23. Some Aspects of Inclusion of Loading History in the Fracture Strength Analysis of Reactor Pressure Vessels Under Thermal Shock Conditions
24. Multifunctional Data Acquisition and Control System Rigging the Beds and Units for Strength Tests of Models and Structure Elements from Composite Materials
25. Experimental Investigation of Mechanical Behavior of Materials by Small Punch Testing of Miniature Disk Specimens
26. Determination of Stress Intensity Factors in the Welded Joint Between the Header and Shell of Pgv-1000m Steam Generator with a Defect in the Form of a Cavity with a Crack
27. Experimental Determination of the Moment of Fracture Initiation in Standard Charpy Specimens and Specimens with Edge Notches
28. On the Determination of the Mechanical Characteristics of Steels from Hardness Test Results
29. Elastoplastic Fracture Resistance Analysis of NPP Primary Circuit Equipment Elements
30. Calculation analysis of the stress-strain state of the collector-to-nozzle weld in the steam generator under seismic loading
31. INTERNATIONAL SCIENTIFIC CONFERENCE STRUCTURAL INTEGRITY AND LIFE OF NPP EQUIPMENT (Resource-2012)
32. Stress-Strain State of the Coolant Collector-to-Nozzle Welded Joint in the PGV-1000M Steam Generator Under the Operating Loads with Consideration of Residual Manufacturing Stresses
33. Investigation on Strength Characteristics of Steam Generator Welded Joint After Operational Life Using Instrumented Indentation Test Method
34. Effect of Pulsed Magnetic Field Treatment on the Fracture Resistance of a Cracked Specimen
35. Effect of transient heating of the outer surface of a radial crack-containing ring specimen on its brittle fracture resistance
36. Relationship between composition, structure, and mechanical properties of a condensed composite of copper–tungsten system
37. Evaluation of the residual stresses in the welded joint of the header with a connecting pipe of a steam generator after additional thermomechanical treatment
38. Relationship between hardness and strength characteristics of Cu–Cr microlayer composite material at elevated temperatures
39. The influence of thermomechanical loading history on the stress level in WWER NPP reactor pressure vessels under thermal shock
40. Redistribution of stresses in the header–PGV-1000 steam generator connector weldment under loading after thermal treatment
41. Deformation and fracture of high-temperature steels at different temperatures and loading rates
42. Numerical simulation of stress-strain state near crack tip in a compact tensile specimen
43. Effect of the layout of small-and large-series WWER-1000 reactors of nuclear power plants on the stress-strain state of the header-steam generator connector weldment
44. 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
45. Stress-strain state of the header-steam generator connector weldment induced by local thermal treatment
46. The effect of temperature and loading rate on the crack initiation and propagation energy in carbon steel charpy specimens
47. System of Strain and Load Measurement in Dynamic Testing of Materials
48. Life Calculations for Header – PGV-1000 Steam Generator Connector Weld Joints under NPP Service Conditions
49. Some Topical Issues of Strength and Life Assessment for Elements of Heavy-Duty NPP Equipment under Thermomechanical Loading
50. Stress-Strain State Evaluation of a Welded Joint of Hot Collector to Nozzle of NPP Steam Generator PGV-1000
Catalog
Books, media, physical & digital resources
Discovery Service for Jio Institute Digital Library
For full access to our library's resources, please sign in.