International Conference “Structural Integrity and Life of NPP Equipment” (SIL-2003) OriginalPaper Pages: 1 - 2
Neutron Embrittlement of WWER Reactors: EC-Supported Projects R. AhlstrandM. BiethC. Rieg OriginalPaper Pages: 3 - 7
Radiation Embrittlement Understanding for PLIM Activities at EC-JRC-IE L. DebarberisF. SeviniM. Valo OriginalPaper Pages: 14 - 18
SCK-CEN Contribution to the IAEA Round Robin Exercise on WWER-440 RPV Weld Material: Irradiation, Annealing, and Re-Embrittlement E. LuconE. van WalleM. Wéber OriginalPaper Pages: 19 - 32
Micromechanical Coupled Study of Crack Growth Initiation Criterion in Pressure Vessel Steel M. RakinA. SedmakS. Sedmak OriginalPaper Pages: 33 - 36
Study of Aging Mechanisms for Structural Materials within SAFELIFE Project F. SeviniL. DebarberisM. Brumovsky OriginalPaper Pages: 37 - 41
Transferability of Laboratory Fracture Data to Safety Assessment of Postulated Defects in Critical NPP Components N. TaylorK. F. Nilsson OriginalPaper Pages: 42 - 46
Fracture Toughness and Crack Resistance of Steam Pipeline Steel in Initial and Used States M. ZrilicZ. BurzicZ. Cvijovic OriginalPaper Pages: 47 - 58
Development of Software for Calculation of Erosion-Corrosion Wear of NPP Reactor Piping V. I. BaranenkoS. G. OleinikA. V. Kumov OriginalPaper Pages: 59 - 62
On Improvement of Methods for Experimental Determination of Strength Characteristics of NPP Component Materials G. S. Vasil'chenkoA. G. KazantsevI. O. Tregubov OriginalPaper Pages: 63 - 70
Assessment of In-Service Degradation of Mechanical Properties of NPP Reactor and Piping Materials G. P. KarzovB. T. TimofeevT. A. Chernaenko OriginalPaper Pages: 71 - 74
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. MamaevaM. B. BakirovO. A. Fedorova OriginalPaper Pages: 75 - 79
Effect of the Anisotropy of Physicomechanical Properties on the Kinetics of Cracks in Austenitic Steels N. A. MakhutovI. V. MakarenkoL. V. Makarenko OriginalPaper Pages: 80 - 84
The Ultimate State of Structural Alloys for Superconducting Electromagnetic System of Thermonuclear Reactor L. S. Novogrudskii OriginalPaper Pages: 85 - 88
Methods for the Evaluation of Corrosion Fatigue of Steels and Alloys V. I. PokhmurskiiM. S. Khoma OriginalPaper Pages: 89 - 93
Fatigue of NPP Components and Piping under Service Conditions V. M. Filatov OriginalPaper Pages: 94 - 100
Some Topical Issues of Strength and Life Assessment for Elements of Heavy-Duty NPP Equipment under Thermomechanical Loading V. V. KharchenkoG. V. StepanovI. V. Orynyak OriginalPaper Pages: 101 - 105
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'zhenkoYu. G. Efremov OriginalPaper Pages: 106 - 112
