DOI QR코드

DOI QR Code

Development of Assessment Methodology on Creep-Fatigue Crack Behavior for a Grade 91 Steel Structure

Mod.9Cr-1Mo 강 구조의 크리프-피로 균열 거동 평가법 개발

  • Published : 2010.01.01

Abstract

In this study, an assessment method on creep-fatigue crack initiation and crack growth for a Mod.9Cr-1Mo steel (ASME Grade 91) structure has been developed with an extension of the French RCC-MR A16 procedure. The current A16 guide provides defect assessment procedure for a creep-fatigue crack initiation and crack growth for an austenitic stainless steel, but no guideline is available yet for a Mod.9Cr-1Mo steel which is now widely being adopted for structural materials of future nuclear reactor system as well as ultra super critical (USC) thermal plant. In the present study an assessment method on creep-fatigue crack initiation and crack growth is provided for the FMS (Ferritic-Martensitic Steel) and assessment on the creep-fatigue crack behavior for a structure has been carried out. The assessment results were compared with the observed images from a structural test.

Keywords

Creep-Fatigue;Crack Growth;Crack Initiation;Mod.9Cr-1Mo Steel;High Temperature Component

References

  1. Hahn, D-H, et. al., 2007, KALIMER-600 Conceptual Design Report, KAERI/TR- 381, Korea Atomic Energy Research Institute, Daejeon
  2. ASME Boiler and Pressure Vessel Code, 2007, Section III, Rules for Construction of Nuclear Power Plant Components, Div. 1, Subsection NH, Class 1 Components in Elevated Temperature Service, ASME
  3. RCC-MR, Section I Subsection B, 2007, Design and Construction Rules for Mechanical Components of Nuclear Installations, AFCEN
  4. High Temperature Structural Design Guideline for Fast Breeder Demonstration Reactor (draft), 1999, JAPC
  5. RCC-MR, Section I Subsection Z,2007, Technical Appendix 16, Design and Construction Rules for Mechanical Components of Nuclear Installations, AFCEN
  6. R5, Assessment Procedure for the High Temperature Response of Structures, Issue 3, 2003, British Energy Generation Ltd.
  7. API579, 2001, API Recommended Practice 579, API
  8. FITNET FITNESS-FOR-SERVICE Procedure, 2008, Rev. MK8, ISBN 978-3-940923-00-4, Jan
  9. Metheron, Ph., Chapuliot, S.,2005, Fatigue Initiation of Crack Under Mode III and Mixed Mode I+III Loads in a 9Cr Steel, 18th Int. Conf. on SMIRT, Beijing, China, pp. 1896-1903, August , p.7
  10. Ancelet, O., Chapuliot, S., 2007, “Mechanical Behavior of HTR Materials : Developments in Support of Defect Assessment, Structural Integrity and Lifetime Evaluation,” Proceedings of ICAPP 2007, Nice, France, May 13-18, Paper 7182
  11. Ancelet, O., Marie, S., 2008,“CEA Developments in Support of High Temperature Defect Assessment, Structural Integrity Lifetime Evaluation,” VAMAS TWA31 Annual Meeting, May, 19th, Imperial College London.
  12. Lee, H-Y, Kim, J-B, Kim, W.-G, Lee, J.-H, 2008, “Creep-Fatigue Crack Behavior of a Mod.9Cr-1Mo Steel Structure with Weldments,” 5th Int. Conf. on Creep-Fatigue Interaction, IGCAR, India, Sept. 24-26
  13. Lee, H-Y, Kim, J-B, Kim, S-H, Lee, J-H., 2006, “Assessment of Creep-Fatigue Crack Initiation for Welded Cylindrical Structure of Austenitic Stainless Steels,” International Journal of Pressure Vessel and Piping, 83, pp.826-834 https://doi.org/10.1016/j.ijpvp.2006.08.009
  14. Lee, H-Y, Lee, J-H., Kim, B-H.,2006, “Creep-Fatigue Crack Growth Behavior of a Structure with Crack Like Defects at the Welds,” Journal of Mechanical Science and Technology, 20(12), pp. 2067~2076
  15. Lee, H-Y, Lee, S-H., Kim, J-B, Kim, Lee, J-H., 2007, “Creep-Fatigue Damage for a Structure with Dissimilar Metal Welds of Mod 9Cr-1Mo and 316L Stainless Steel,” International Journal of Fatigue, 29, pp.1868-1879. https://doi.org/10.1016/j.ijfatigue.2007.02.009
  16. Lee, H-Y, Lee, J-H., Nikbin, K., 2009, “Assessment of High Temperature Crack Behavior for a Structure with Defects,” Journal of Pressure Vessel Technology, Transactions of ASME,Vol.131, pp.031403-1-7, June
  17. RCC-MR, Section I Subsection Z,2007, Technical Appendix 3, Design and Construction Rules for Mechanical Components of Nuclear Installations, AFCEN
  18. ABAQUS Ver. 6.7, 2008, Simulia

Cited by

  1. High-Temperature Design of Sodium-to-Air Heat Exchanger in Sodium Test Loop vol.37, pp.5, 2013, https://doi.org/10.3795/KSME-A.2013.37.5.665