Published August 2014 | Version v1
Journal article

Thermal transient test and strength evaluation of a tubesheet structure made of Mod.9Cr–1Mo steel. Part II: Creep-fatigue strength evaluation

  • 1. Japan Atomic Energy Agency, Oarai-cho, Higashi-ibaraki, Ibaraki 311-1393 (Japan)
  • 2. Mitsubishi Heavy Industries, Ltd., Hyogo-ku, Kobe, Hyogo 676-8585 (Japan)
  • 3. Mitsubishi FBR Systems, Inc., Jingumae, Shibuya-ku, Tokyo 150-0001 (Japan)

Description

Highlights: • The strength of a tubesheet model subjected to cyclic thermal transients was evaluated. • Heat transfer analysis and stress analysis were performed. • The failure life was evaluated by the several methods using finite element analyses. • Failure life could be predicted within a factor of 3 using the inelastic finite element analyses. - Abstract: The tubesheet structure is one of the components that suffer the most severe loading in fast reactors, and it is one of the most difficult components to design because of such severe operation conditions and its complex three-dimensional structure with an arrangement of numerous penetration holes. In this study, the strength of a tubesheet test model simulating a semispherical tubesheet structure subjected to cyclic thermal transients was evaluated using the finite element analysis (FEA). A test model made of Mod.9Cr–1Mo steel was subjected to 1873 cycles of severe thermal transient loading using a large-scale sodium loop, in which elevated-temperature sodium at 600 °C and 250 °C was flowed repeatedly and kept at the final temperature for 2 and 1 h, respectively. Heat transfer analysis and stress analysis were performed using the sodium temperature data measured during the test. The boundary conditions were adjusted to simulate the measured temperature distribution on the inner and outer surfaces of the test model in the heat transfer analysis, and the result was used for the stress analysis. Then, the elastic and inelastic stress analysis results were used to investigate the failure mechanism by creep-fatigue damage and evaluate the failure strength. The evaluation based on the results of inelastic analysis estimated the number of cycles to failure within a factor of 3 of the total number of thermal loading cycles 1873, which corresponds to the number of cycle at which the crack reached 2.59 mm

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2014.04.029

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2014.04.029;
PII
S0029-5493(14)00254-4;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
275
Journal Page Range
p. 422-432
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.