Evaluation and Test of the Creep-Fatigue Defect Growth in a Cylindrical Structure in a Liquid Metal Reactor

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This paper deals with the creep-fatigue defect growth behavior at the defect front of a high temperature cylindrical structure subjected to a cyclic axial tensile loading and a thermal loading in the LMR(Liquid Metal Reactor) structures. The defect growth evaluation was carried out per the France RCC-MR A16 guide and UK R5 code and their results were compared. The creepfatigue structural test to confirm the evaulated results was carried out with a induction heater. The defect front was investigated at every 100th cycle of a testing by using the metallurgical inspection technique with an optical microscope. From these results, we showed that the creep-fatigue defect behavior of a high temperature structure can be predicted with a conservatism by following the RCC-MR A16 guide and the R5 code.

Info:

Periodical:

Key Engineering Materials (Volumes 326-328)

Edited by:

Soon-Bok Lee and Yun-Jae Kim

Pages:

1015-1018

DOI:

10.4028/www.scientific.net/KEM.326-328.1015

Citation:

C. G. Park et al., "Evaluation and Test of the Creep-Fatigue Defect Growth in a Cylindrical Structure in a Liquid Metal Reactor", Key Engineering Materials, Vols. 326-328, pp. 1015-1018, 2006

Online since:

December 2006

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Price:

$38.00

[1] D. Hahn, et al. : Design Features of Advanced Sodium-Cooled Fast Reactor KALIMER-600, Proceedings of ICAPP'04, Pittsburgh, USA (2004).

[2] Appendix A16 : Guide for Leak Before Break Analysis and Defect Assessment, AFCEN (2002).

[3] R5, Assessment Procedure for the High Temperature Response of Structures, British Energy (2003).

[4] C. G. Park, J. B. Kim, H. Y. Lee, J. H. Lee : Evaluation and Test of a Crack Initiation for a 316SS Cylindrical Y-junction Structure in a Liquid Metal Reactor, Korea Nuclear Society, Proceedings of Spring Conference, Korea(2005).

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