| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of Relationship Between the Radiation Embrittlement Mechanisms and the Influence of Neutron Flux in Respect of WWER Reactor Pressure Vessel Materials
|
Margolin, B. Z.
|
|
2013
|
45 |
4 |
p. 406-423
|
artikel
|
| 2 |
Application of the Beremin Model for Cruciform Specimen to Determine the Fracture Probability in Case of WPS
|
Beleznai, R.
|
|
2013
|
45 |
4 |
p. 489-494
|
artikel
|
| 3 |
Approaches to Substantiated Service Life Extension for BN Reactors
|
Vasil’ev, B. A.
|
|
2013
|
45 |
4 |
p. 442-447
|
artikel
|
| 4 |
A Study of the Causes of the Service Fracture of Turbine Rotor Blade of Compressor Station Gas-Turbine Unit
|
Krasovs’kyi, A. Ya.
|
|
2013
|
45 |
4 |
p. 466-470
|
artikel
|
| 5 |
Calculation analysis of the stress-strain state of the collector-to-nozzle weld in the steam generator under seismic loading
|
Khodakovskii, A. A.
|
|
2013
|
45 |
4 |
p. 482-488
|
artikel
|
| 6 |
Calculation-and-Experimental Assessment of the Serviceability of Pipe Elements Under Operating Conditions
|
Kravchuk, L. V.
|
|
2013
|
45 |
4 |
p. 471-476
|
artikel
|
| 7 |
Determination of Mechanical Properties of Aged NPP Components Using Instrumented Hardness Testing and Other Miniature Specimen Testing Techniques
|
Lenkey, G. B.
|
|
2013
|
45 |
4 |
p. 433-441
|
artikel
|
| 8 |
Development of Ultrasonic Tomography Techniques for Diagnostics of Nuclear Power Plant Piping
|
Koshovyi, V. V.
|
|
2013
|
45 |
4 |
p. 512-516
|
artikel
|
| 9 |
Elastoplastic Fracture Resistance Analysis of NPP Primary Circuit Equipment Elements
|
Kharchenko, V. V.
|
|
2013
|
45 |
4 |
p. 397-405
|
artikel
|
| 10 |
Embrittlement Behavior of the RPV Metal of Power Unit No. 2 at the Zaporozhye NPP
|
Revka, V. M.
|
|
2013
|
45 |
4 |
p. 477-481
|
artikel
|
| 11 |
INTERNATIONAL SCIENTIFIC CONFERENCE STRUCTURAL INTEGRITY AND LIFE OF NPP EQUIPMENT (Resource-2012)
|
Kharchenko, V. V.
|
|
2013
|
45 |
4 |
p. 391
|
artikel
|
| 12 |
Interpretation of Accelerated Irradiation Results for Materials of WWER-1000 Reactor Pressure Vessels
|
Erak, D. Yu.
|
|
2013
|
45 |
4 |
p. 424-432
|
artikel
|
| 13 |
Methodology and Software Package for Assessment of Stress-strain State Parameters of Full-Scale Structures and Its Application to a Study of Loading Level, Defect Rate, and Residual Stress Level in Elements of NPP Equipment
|
Chernyatin, A. S.
|
|
2013
|
45 |
4 |
p. 506-511
|
artikel
|
| 14 |
Methodology for Lifetime Assessment of Reactor Plant Equipment and Systems Based on Damaged Medium Mechanics
|
Mitenkov, F. M.
|
|
2013
|
45 |
4 |
p. 448-453
|
artikel
|
| 15 |
RPV Long Term Operation: Open Issues
|
Ballesteros, A.
|
|
2013
|
45 |
4 |
p. 392-396
|
artikel
|
| 16 |
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
|
Chirkov, A. Yu.
|
|
2013
|
45 |
4 |
p. 459-465
|
artikel
|
| 17 |
Studies on the Fracture Mechanism and Kinetics of Randomly Oriented Surface Semielliptic Cracks at the Multiaxial Stress–strain State with Deformation Criteria of Nonlinear Fracture Mechanics
|
Makhutov, N. A.
|
|
2013
|
45 |
4 |
p. 454-458
|
artikel
|
| 18 |
Unified Model of Steady-State and Transient Creep and Identification of Its Parameters
|
Katanakha, N. A.
|
|
2013
|
45 |
4 |
p. 495-505
|
artikel
|
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