Simulation of Fatigue Processes in the Structural Materials of Reactor Vessels Over a 102 – 1012 Cycle Durability Range*
Source abstract
Abstract
The aggregate model of the evolutionary equation for fatigue damage accumulation in the structural materials of reactor vessels suffering from low- and high-cycle fatigue is presented. The reliability of the model is substantiated by comparing numerical results and experimental data.
The source flagged this abstract for review. Check formulas and completeness against the original publication.
Source: openaire · Quality: needs review · Source record ↗
Source flags: short_text
Source flags: short_text
Research context
OpenAlex topics: Nuclear Materials and Properties · Fatigue and fracture mechanics · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (3)
Show source-provided references
1. F. M. Mitenkov, V. B. Kaidalov, and Yu. G. Korotkikh, Methods of Substantiating the Life of Nuclear Power Reactors [in Russian], Mashinostroenie, Moscow (2007).
2. V. T. Troshchenko and P. A. Fomichev, “An energy criterion for fatigue failure,” Strength Mater., 25, No. 1, 1–7 (1993).10.1007/BF00767729 ↗
3. L. A. Khamaza and V. A. Kovalenko, “Resistance of metals to fatigue failure and deformation during two-frequency loading. Report 1. Test methods and results on the fatigue and inelasticity of metals during two-frequency cyclic loading,” Strength Mater., 21, No. 10, 1285–1292 (1989).10.1007/BF01529252 ↗