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http://dx.doi.org/10.5516/NET.09.2011.031

FATIGUE ANALYSIS OF A REACTOR PRESSURE VESSEL FOR SMART  

Jhung, Myung-Jo (Research Management Department, Korea Institute of Nuclear Safety)
Publication Information
Nuclear Engineering and Technology / v.44, no.6, 2012 , pp. 683-688 More about this Journal
Abstract
The structural integrity of mechanical components during several transients should be assured in the design stage. This requires a fatigue analysis including thermal and stress analyses. As an example, this study performs a fatigue analysis of the reactor pressure vessel of SMART during arbitrary transients. Using heat transfer coefficients determined based on the operating environments, a transient thermal analysis is performed and the results are applied to a finite element model along with the pressure to calculate the stresses. The total stress intensity range and cumulative fatigue usage factor are investigated to determine the adequacy of the design.
Keywords
Reactor Pressure Vessel; Heat Transfer Coefficient; Fatigue; Stress Concentration Factor; Fatigue Curve; Rain-flow Method; Cumulative usage Factor;
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  • Reference
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