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Kharchenko V.V.,Ukrainian Academy of Sciences | Chirkov A.Yu.,Ukrainian Academy of Sciences | Kobel'Skii S.V.,Ukrainian Academy of Sciences | Kravchenko V.I.,Ukrainian Academy of Sciences | And 2 more authors.
Strength of Materials | Year: 2010

We present the results of calculations of the kinetics of stress-strain state and stress intensity factors for surface and under-the-cladding circumferential cracks in modeling the emergency core cooldown conditions for the WWER-1000 reactor. The calculation procedure is based on a mixed finite-element method statement which provides stability of numerical solution and a high accuracy of results for both the displacements as well as stresses and strains. The authors analyze the influence of the density of the finite-element discretization of the crack-tip area for the surface and under-the-cladding circumferential cracks on the accuracy and convergence of computation of fracture-mechanics parameters in the modeling of thermal shock conditions. The results of calculation of kinetics of stress intensity factors allowing for the thermomechanical loading history and residual process-induced stress fields are reported. It is demonstrated that if the elastoplastic deformation history and residual process-induced stress fields are disregarded in the calculations of stress intensity factors for under-the-cladding cracks the reactor pressure vessel strength and lifetime may turn out to be overestimated. © 2010 Springer Science+Business Media, Inc. Source


Berkovich V.Ya.,Open Joint Stock Company OKB Gidropress | Bogachev A.V.,Open Joint Stock Company OKB Gidropress | Dranchenko B.N.,Open Joint Stock Company OKB Gidropress | Semishkin V.P.,Open Joint Stock Company OKB Gidropress
Strength of Materials | Year: 2010

We generalize the software implementation experience for a SAKOR-M system of automated monitoring of the residual service life operating as a component of the systems of diagnostics of residual service life. The SAKOR-320 system introduced at the second power-generating block of the Rostovskaya nuclear power plant additionally includes the surface resistance thermometers, solves the inverse problem, takes into account the actual displacements of steam generators, computes the degree of fatigue growth of the defects, and evaluates the ultimate states according to the criteria of leak prior to failure. © 2010 Springer Science+Business Media, Inc. Source

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