1. International Conference “Structural Integrity and Life of NPP Equipment” (SIL-2003)

   OriginalPaper Pages: 1 - 2

2. Neutron Embrittlement of WWER Reactors: EC-Supported Projects

   • R. Ahlstrand
   • M. Bieth
   • C. Rieg

   OriginalPaper Pages: 3 - 7

3. Beyond RPV Design Life

   • A. Ballesteros
   • G. Garcia
   • J. Bros

   OriginalPaper Pages: 8 - 13

4. Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE

   • L. Debarberis
   • F. Sevini
   • M. Valo

   OriginalPaper Pages: 14 - 18

5. SCK-CEN Contribution to the IAEA Round Robin Exercise on WWER-440 RPV Weld Material: Irradiation, Annealing, and Re-Embrittlement

   • E. Lucon
   • E. van Walle
   • M. Wéber

   OriginalPaper Pages: 19 - 32

6. Micromechanical Coupled Study of Crack Growth Initiation Criterion in Pressure Vessel Steel

   • M. Rakin
   • A. Sedmak
   • S. Sedmak

   OriginalPaper Pages: 33 - 36

7. Study of Aging Mechanisms for Structural Materials within SAFELIFE Project

   • F. Sevini
   • L. Debarberis
   • M. Brumovsky

   OriginalPaper Pages: 37 - 41

8. Transferability of Laboratory Fracture Data to Safety Assessment of Postulated Defects in Critical NPP Components

   • N. Taylor
   • K. F. Nilsson

   OriginalPaper Pages: 42 - 46

9. Fracture Toughness and Crack Resistance of Steam Pipeline Steel in Initial and Used States

   • M. Zrilic
   • Z. Burzic
   • Z. Cvijovic

   OriginalPaper Pages: 47 - 58

10. Development of Software for Calculation of Erosion-Corrosion Wear of NPP Reactor Piping

    • V. I. Baranenko
    • S. G. Oleinik
    • A. V. Kumov

    OriginalPaper Pages: 59 - 62

11. On Improvement of Methods for Experimental Determination of Strength Characteristics of NPP Component Materials

    • G. S. Vasil'chenko
    • A. G. Kazantsev
    • I. O. Tregubov

    OriginalPaper Pages: 63 - 70

12. Assessment of In-Service Degradation of Mechanical Properties of NPP Reactor and Piping Materials

    • G. P. Karzov
    • B. T. Timofeev
    • T. A. Chernaenko

    OriginalPaper Pages: 71 - 74

13. Degradation of the Properties and Structure of Welded Joints of Pipelines in WWER-440 Reactors in the Process of Heat and Heat-Strain Aging under Conditions of Long-Term Operation

    • E. I. Mamaeva
    • M. B. Bakirov
    • O. A. Fedorova

    OriginalPaper Pages: 75 - 79

14. Effect of the Anisotropy of Physicomechanical Properties on the Kinetics of Cracks in Austenitic Steels

    • N. A. Makhutov
    • I. V. Makarenko
    • L. V. Makarenko

    OriginalPaper Pages: 80 - 84

15. The Ultimate State of Structural Alloys for Superconducting Electromagnetic System of Thermonuclear Reactor

    • L. S. Novogrudskii

    OriginalPaper Pages: 85 - 88

16. Methods for the Evaluation of Corrosion Fatigue of Steels and Alloys

    • V. I. Pokhmurskii
    • M. S. Khoma

    OriginalPaper Pages: 89 - 93

17. Fatigue of NPP Components and Piping under Service Conditions

    • V. M. Filatov

    OriginalPaper Pages: 94 - 100

18. Some Topical Issues of Strength and Life Assessment for Elements of Heavy-Duty NPP Equipment under Thermomechanical Loading

    • V. V. Kharchenko
    • G. V. Stepanov
    • I. V. Orynyak

    OriginalPaper Pages: 101 - 105

19. Development of the Method for Automated Estimation of the Effect of Operational Parameters on a Vibration State of a Turbo-Generator Set

    • N. G. Shul'zhenko
    • Yu. G. Efremov

    OriginalPaper Pages: 106 - 112