Abstract
This paper presents an improved methodology for determining high-temperature tensile design strengths of Alloy 617, which is regarded as one of main structural materials for very high temperature reactor (VHTR) system. In establishing time-independent allowable stress values, an existing ASME standard procedure is preliminarily analyzed and their limitations are pointed out. Then, an improved methodology, which has a consistent and quantifiable design margin at low and high temperatures for tensile strengths, is proposed and compared with the ASME method. To find suitable curves of temperature trend to the tensile strength data, three fitting methods are demonstrated, and a statistical technique is adopted for design use. The results will be utilized to reasonably determine the tensile design strengths of Alloy 617 for application in the VHTR system.
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W. G. Kim, S. N. Yin, Y. W. Kim and J. H. Chang, Creep properties and creep life prediction of Alloy 617 for a very high temperature gas-cooled reactor, Proc. of ASME PVP 2008 Conf., Chicago, USA, July (2008) Paper PVP 2008-61356.
S. J. Dewson and X. Li, Selection criteria for the high temperature reactor intermediate heat exchanger, Proc. of ICAPP 05, Seoul, Korea, May (2005) Paper 5333.
W. G. Kim, S. N. Yin, W. Y. Kim and J. H. Chang, Creep characterization of a Ni-based Hastelloy-X alloy by using theta projection method, Engineering Fracture Mechanics, 75 (2008) 4985–4995.
W. G. Kim, S. N. Yin, G. G. Lee, Y. W. Kim and S. J. Kim, Creep oxidation behavior and creep strength prediction for Alloy 617, Int. J. of Pressure Vessels and Piping, 87 (2010) 289–295.
J. M. Corum and J. J. Blass, Rules for design of alloy 617 nuclear components to very high temperatures, Attachment 2, Draft Code Case for Alloy 617, USA (1988).
W. G. Kim, S. N. Yin, W. S. Ryu and J. H. Chang, Analysis of the creep rupture data of Alloy 617 for a high temperature gas cooled reactor, The 8th Int. Conf. on Creep and Fatigue at Elevated Temperatures, Texas, USA, July (2007) Paper PVP 2007-26834.
J. H. Chang, Y. W. Kim, K. Y. Lee, Y. W. Lee, W. J. Lee, J. M. Noh, M. W. Kim, H. S. Lim, Y. J. Shin, K. K. Bae and K. D. Jung, A study of a nuclear hydrogen production demonstration plant, Nuclear Engineering and Technology, 39(2) (2007) 111–122.
H. Y. Lee, Y. W. Kim, and K. N. Song, Preliminary application of the draft code case for alloy 617 for a high temperature component, J. of Mechanical Science and Technology, 22 (2008) 856–863.
J. Y. Park, D. W. Kim, D. J. Kim, E. S. Kim, H. P. Kim, S. H. Kim, W. J. Kim, W. G. Kim, W. S. Ryu and Y. D. Kim, Development of materials for a high temperature gas cooled reactor in Korea, The 4th International Topical Meeting on High Temperature Reactor Technology-HTR 2008, Washington, USA (2008) Paper HTR 2008-58149.
Draft Alloy 617 code case, Task Force Very High Temperature Design, ASME (1988).
T. L. Sham, D. R. Eno and K. P. Jensen, Treatment of high temperature tensile data for Alloy 617 and Alloy 230, Proc. of ASME PVP 2008. Chicago, USA, July (2008) Paper PVP 2008-61128.
ASME boiler and pressure vessel code, Section II, Part D, ASME, USA, New York (2007).
European Alloy-DB, Licensed CD, European Commission, Joint Research Centre (JRC).
W. G. Kim. D. W. Kim, W. S. Ryu, C. H. Han, J. H. Yoon and J. Chang, Mechanical property and its comparison of superalloys for high temperature gas cooled reactor, KAERI report, KAERI/AR-723/2005 (2005).
http://www.specialmetals.com (2008).
http://www.haynesintl.com (2008).
D. W. Kim, Effect of nitrogen on dynamic strain ageing and high temperature low cycle fatigue properties in type 316L stainless steel, the Ph.D thesis at KAIST, Daejeon (1998) 33–38.
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This paper was recommended for publication in revised form by Editor
Woo-Gon Kim received his Ph.D from Chungbuk National University in the Dept. of Mechanical Engineering in 1999. As principal researcher at Korea Atomic Energy Research Institute, his specialty is mechanical assessment, analysis, modeling and database establishment of high temperature nuclear materials for Gen-IV reactor systems, and especially, timedependent creep and crack growth behaviors at elevated temperature.
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Kim, WG., Yin, SN., Park, JY. et al. An improved methodology for determining tensile design strengths of Alloy 617. J Mech Sci Technol 26, 379–387 (2012). https://doi.org/10.1007/s12206-011-1024-5
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DOI: https://doi.org/10.1007/s12206-011-1024-5