Published August 2012 | Version v1
Journal article

Fatigue analysis of a reactor pressure vessel for SMART

  • 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

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.

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Technology
Journal Volume
44
Journal Issue
6
Series
7 refs, 10 figs, 2 tabs
Journal Page Range
p. 683-688
ISSN
1738-5733