13th International Conference on Fracture June 16–21, 2013, Beijing, China -10- Figure 5. Summary of Properties for Grade 91 steel contained in the data workbook, EPRI report 1019778 References [1]. ASME, “Rules for the Construction of Nuclear Facility Components, Class 1 Components in Elevated Temperature Service, Boiler and Pressure Code, Section III, Division 1— Subsection NH” (2001). [2]. TRD 301, “Annex I—Design: Calculation for Cyclic Loading due to Pulsating Internal Pressure or Combined Changes of Internal Pressure and Temperature,” in Technical Rules for Steam Boilers (1978). [3]. RCC-MR, Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, Section I—Nuclear Islands Components Edition. AFCEN (1985). [4]. R. A. Ainsworth, et al. (eds.), R5, An Assessment Procedure for the High Temperature Response of Structures, Barnwood: British Energy Generation (2003). [5]. Standard Test Method for Creep-Fatigue Testing, ASTM, Designation: E 2714 – 09. [6]. S.R. Holdsworth, R.P. Skelton, B. Dogan. “Code of practice for the measurement and analysis of high strain creep-fatigue short crack growth.” Materials at High Temperature 27(4), 2010. 265-283. [7]. Program on Technology Innovation: Evaluation of the Creep-Fatigue Behavior of Grade 92 Steel and Its Predictability. EPRI, Palo Alto, CA: 2011. 1024588.
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