Structural integrity and life of npp equipment (Resource-2009) V. V. Bukhanovskii International Conference 09 February 2010 Pages: 1 - 1
A new approach to description of in-service embrittlement of WWER-1000 reactor pressure vessel materials B. Z. MargolinV. A. NikolaevA. V. Nikolaeva Scientific and Technical Section 09 February 2010 Pages: 2 - 16
The influence of thermomechanical loading history on the stress level in WWER NPP reactor pressure vessels under thermal shock V. V. KharchenkoA. Yu. ChirkovI. F. Akbashev OriginalPaper 09 February 2010 Pages: 17 - 24
A study of fracture kinetics in welded components of nuclear power plant equipment in the presence of surface semi-elliptical variously oriented cracks N. A. MakhutovI. V. MakarenkoL. V. Makarenko OriginalPaper 06 February 2010 Pages: 25 - 31
Assessment of brittle strength of nuclear reactor pressure vessel steel upon warm prestressing P. V. YasniiI. B. OkipnyiYu. I. Pyndus OriginalPaper 06 February 2010 Pages: 32 - 37
Evolution of the structure of the WWER-1000 reactor vessel from the prototype model to WWER-1200 V. I. BakaldinV. I. KashirinV. G. Fedosov OriginalPaper 09 February 2010 Pages: 38 - 43
Application of the system of automated monitoring of the residual service life for the solution of the problems of operation of nuclear power plants with water-cooled water-moderated reactors V. Ya. BerkovichA. V. BogachevV. P. Semishkin OriginalPaper 09 February 2010 Pages: 44 - 50
Lifetime analysis of wwer reactor pressure vessel internals concerning material degradation Ju. DudraSz. Szávai OriginalPaper 09 February 2010 Pages: 51 - 57
Approaches of fracture mechanics in the analysis of admissible defects in the form of notches Yu. G. Matvienko OriginalPaper 09 February 2010 Pages: 58 - 63
Electrochemical behavior of 15Kh2NMFA steel in borate-buffered reactor water at temperatures of 22–300°C under equilibrium pressures V. I. Pokhmurs’kyiI. M. AntoshchakE. I. Lychkovs’ky OriginalPaper 09 February 2010 Pages: 64 - 69
Study of the beltline weld and base metal of WWER-440 first generation reactor pressure vessel J. SchuhknechtU. RindelhardtH.-W. Viehrig OriginalPaper 13 February 2010 Pages: 70 - 77
Study of irradiation effects at the research reactor F. Gillemot OriginalPaper 10 February 2010 Pages: 78 - 83
Ductility and cold resistance of structural steels S. A. KotrechkoYu. Ya. MeshkovA. V. Shiyan OriginalPaper 10 February 2010 Pages: 84 - 89
The kinetics of damage accumulation in heat-resistant steels under different loading conditions F. F. GiginyakP. A. BulakhT. N. Mozharovskaya OriginalPaper 10 February 2010 Pages: 90 - 94
Experimental study of variation of 08Kh18N12T steel properties in the npp main circulating pipeline during its operation L. A. SosnovskiiA. V. BogdanovichV. G. Barsukov OriginalPaper 10 February 2010 Pages: 95 - 100
Ultimate exhaustion of local plasticity as a criterion of fatigue crack initiation G. V. TsybanevA. I. Novikov OriginalPaper 10 February 2010 Pages: 101 - 107
Fatigue damage and failure of steam turbine rotors by torsional vibrations A. P. BovsunovskiiO. Yu. ChernousenkoD. A. Bashta OriginalPaper 10 February 2010 Pages: 108 - 113
Thermostressed state and crack growth resistance of rotors of the NPP turbine K-1000-60/1500 M. G. Shul’zhenkoP. P. GontarovskyiT. V. Protasova OriginalPaper 10 February 2010 Pages: 114 - 119
Analysis of warm prestressing effect on fracture toughness of reactor pressure vessel steels R. BeleznaiSz. Szávai OriginalPaper 10 February 2010 Pages: 120 - 123
Information technologies for vibration strength analysis of the Rovenskaya nuclear power plant main steam line E. V. ShtefanM. B. ShamisI. N. Litovchenko OriginalPaper 10 February 2010 Pages: 124 - 128
