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TECHNICAL PAPERS

Elevated-Temperature Mechanical Properties of an Advanced-Type 316 Stainless Steel

[+] Author and Article Information
Charles R. Brinkman

Metals and Ceramics Division, Oak Ridge National Laboratory,2 Oak Ridge, TN 37831-6154e-mail: brinkmancr@ornl.gov

J. Pressure Vessel Technol 123(1), 75-80 (Oct 20, 2000) (6 pages) doi:10.1115/1.1343911 History: Received January 01, 2000; Revised October 20, 2000
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References

Miura, M., Inagaki, T., and Kobayashi, T., 1993, “Present Status of DFBR Design in Japan,” Proc., 4th Annual Scientific and Technical Conference of the Nuclear Society, Nuclear Energy and Human Safety (NE-93), June 28–July 2, Nizhni Novgorod, Russia.
Asada, Y., Ueta, M., Kanaoka, T., Sukekawa, M., and Nishida, T., 1992, “Current Status of the Development of Advanced 316-Steel for FBR Structures,” Stress Classification, Robust Methods, and Elevated Temperature Design, ASME PVP-Vol. 230, pp. 61–65.
Brinkman,  C. R., Sikka,  V. K., and King,  R. T., 1977, “Mechanical Properties of Liquid Metal Fast Breeder Reactor Primary Piping Materials,” Nucl. Technol., 33, Apr., pp. 76–95.
Kaguchi, H., 1998, personal communication, Mitsubishi Heavy Industries, Ltd., Kobe, Japan, July.
Brinkman,  C. R., 1985, “High-Temperature Time-Dependent Fatigue Behavior of Several Engineering Structural Alloys,” Int. Met. Rev., 30, No. 5, pp. 235–58.
Schirra, M. and Heger, S., 1990, “Zeitstandestigketts-und Kriechversuche am EFR-Strakurwerkstoff 316L(N), Din 1.4909,” KFK 4767, Institut für Material-und Festkorperförschung Projekt Nukleare Sicherheits forschung, Kenfurschung-szentrum, Karlsruhe, Germany, Sept.
Schirra, M., Heger, S., Ritter, M., de las Rivas, M., and Chamero, A., 1991, “Untersachungen zum zeitstandfestigkeits-und Kriechverhalten am Austenitischen Stahl AISI 316-NET Abschlußbericht,” KfK 4861, Kernforschungszentrum, Karlsruhe, Germany, Aug.
Nishida, T., Ohno, K., Niinobe, S., Sukekawa, M., and Hirayama, H., 1993, “Elevated Temperature Properties and Micro Structure of 316FR,” Proc., Annual Meeting of JSME/MMD.
Rabbe, P. and Heritier, J., 1979, “Development of Austenitic Stainless Steels with Controlled Residual Nitrogen Content: Application to Nuclear Energy,” Properties of Austenitic Stainless Steels and Their Weld Metals (Influence of Slight Chemistry Variations), ASTM 679, eds., C. R. Brinkman and H. W. Garvin, pp. 124–141.
Brinkman, C. R., 1985, “Fatigue Behavior of Materials in Support of ASME Code Development,” Pressure Vessel and Piping Technology 1985, A Decade of Progress, ASME, pp. 497–506.
Kawasaki, N., 1998, personal communication, The Japan Atomic Power Company, Chiyoda-ku, Tokyo 100, Japan, July.
Brinkman,  C. R., Korth,  G. E., and Hobbins,  R. R., 1972, “Estimates of Creep-Fatigue Interaction in Irradiated and Unirradiated Austenitic Stainless Steel,” Nucl. Technol., 16, Oct. pp. 297–315.
Ueta, M., Nishida, T., Hiroyuki, K., Sukekawa, M., and Taguchi, K., 1995, “Creep-Fatigue Properties of Advanced 316-Steel for FBR Structures,” Paper No. CS22.2, Proc., ASME/PVP, 1995.

Figures

Grahic Jump Location
Comparison of creep-rupture ductilities at two temperatures from data for type 316FR stainless steel generated at ORNL and in Japan
Grahic Jump Location
Comparison of minimum creep rate data for type 316FR stainless steel generated at ORNL and in Japan with estimates based on the Japanese-98 FME equation at three temperatures
Grahic Jump Location
Comparison of creep-rupture data for types 316FR and 316L(N) stainless steel with the ORNL creep-rupture equation for type 316 stainless steel at three temperatures
Grahic Jump Location
Comparison of continuous-cycle fatigue data at 500°C generated at ORNL and in Japan for type 316FR stainless steel (plate and forging) with estimates based on the Japanese-98 FME fatigue equation. Data for type 316 stainless steel are also shown for comparison purposes.
Grahic Jump Location
Creep-fatigue data for types 316 and 316FR stainless steel generated at 593 to 600°C
Grahic Jump Location
Creep-fatigue data for types 316 and 316FR stainless steel generated at 550°C and at a strain range of 1 percent, and plotted as cycles to failure as a function of hold time
Grahic Jump Location
Comparison of continuous-cycle fatigue data at 600°C generated at ORNL and in Japan for type 316FR stainless steel (plate and forging) with estimates based on the Japanese-98 FME fatigue equation. Data for type 316 stainless steel and an equation for this material are also given for comparison purposes.
Grahic Jump Location
Comparison of continuous-cycle fatigue data at 550°C generated at ORNL and in Japan for type 316FR stainless steel (plate and forging) with estimates based on the Japanese-98 FME fatigue equation. Data for type 316 stainless steel and an equation for this material are given for comparison purposes.
Grahic Jump Location
Comparison of creep-rupture data for type 316FR stainless steel generated at ORNL and in Japan with predictions based on the Japanese-98 FME equation
Grahic Jump Location
Yield strength (a) and tensile strength (b) of type 316FR stainless steel as a function of temperature and strain rate

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