Strength of Materials

Structural integrity and life of npp equipment (Resource-2009)

A new approach to description of in-service embrittlement of WWER-1000 reactor pressure vessel materials

B. Z. Margolin, V. A. Nikolaev, E. V. Yurchenko, Yu. A. Nikolaev, D. Yu. Erak, A. V. Nikolaeva

The influence of thermomechanical loading history on the stress level in WWER NPP reactor pressure vessels under thermal shock

V. V. Kharchenko, A. Yu. Chirkov, S. V. Kobel’skii, V. I. Kravchenko, V. A. Piminov, I. F. Akbashev

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. Makhutov, I. V. Makarenko, L. V. Makarenko

Assessment of brittle strength of nuclear reactor pressure vessel steel upon warm prestressing

P. V. Yasnii, I. B. Okipnyi, Yu. I. Pyndus

Evolution of the structure of the WWER-1000 reactor vessel from the prototype model to WWER-1200

V. I. Bakaldin, V. I. Kashirin, V. V. Petrov, V. G. Fedosov

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. Berkovich, A. V. Bogachev, B. N. Dranchenko, V. P. Semishkin

Lifetime analysis of wwer reactor pressure vessel internals concerning material degradation

Ju. Dudra, Sz. Szávai

Approaches of fracture mechanics in the analysis of admissible defects in the form of notches

Yu. G. Matvienko

Electrochemical behavior of 15Kh2NMFA steel in borate-buffered reactor water at temperatures of 22–300°C under equilibrium pressures

V. I. Pokhmurs’kyi, I. M. Antoshchak, V. I. Vorobel’, E. I. Lychkovs’ky

Study of the beltline weld and base metal of WWER-440 first generation reactor pressure vessel

J. Schuhknecht, U. Rindelhardt, H.-W. Viehrig

Study of irradiation effects at the research reactor

F. Gillemot

Ductility and cold resistance of structural steels

S. A. Kotrechko, Yu. Ya. Meshkov, A. V. Shiyan

The kinetics of damage accumulation in heat-resistant steels under different loading conditions

F. F. Giginyak, P. A. Bulakh, T. N. Mozharovskaya

Experimental study of variation of 08Kh18N12T steel properties in the npp main circulating pipeline during its operation

L. A. Sosnovskii, A. V. Bogdanovich, V. G. Barsukov

Ultimate exhaustion of local plasticity as a criterion of fatigue crack initiation

G. V. Tsybanev, A. I. Novikov

Fatigue damage and failure of steam turbine rotors by torsional vibrations

A. P. Bovsunovskii, O. Yu. Chernousenko, E. V. Shtefan, D. A. Bashta

Thermostressed state and crack growth resistance of rotors of the NPP turbine K-1000-60/1500

M. G. Shul’zhenko, P. P. Gontarovskyi, N. G. Garmash, I. I. Melezhyk, T. V. Protasova

Analysis of warm prestressing effect on fracture toughness of reactor pressure vessel steels

R. Beleznai, Sz. Szávai

Information technologies for vibration strength analysis of the Rovenskaya nuclear power plant main steam line

E. V. Shtefan, M. B. Shamis, I. N. Litovchenko