Published August 2012
| Version v1
Journal article
Fatigue analysis of a reactor pressure vessel for SMART
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
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 44079561
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DESIGN; FATIGUE; FINITE ELEMENT METHOD; HEAT TRANSFER; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR VESSELS; STRESS ANALYSIS; THERMAL ANALYSIS; TRANSIENTS
- Descriptors DEC
- CALCULATION METHODS; CONTAINERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS