Elevated-temperature mechanical properties of an advanced type 316 stainless steel

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 391, Issue , 1999, Pages 87-94

  Brinkman, Charles R ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BREEDER REACTORS; CREEP TESTING; FAST REACTORS; FATIGUE TESTING; HIGH TEMPERATURE TESTING; RESEARCH REACTORS; STEEL TESTING; STRAIN; TENSILE TESTING;

CREEP-RUPTURE TESTS; DEMONSTRATION FAST BREEDER REACTORS (DFBR); STAINLESS STEEL 316;

STAINLESS STEEL;

EID: 0033342948     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (13)

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2. Brinkman, C. R., Korth, G. E., and Hobbins, R. R.,October 1972, "Estimates of Creep-Fatigue Interaction in Irradiated and Unirradiated Austenitic Stainless Steel," Nuclear Technology, Vol. 16, pp. 297-315.
3. Brinkman, C. R., 1985a, "High-Temperature Time-Dependent Fatigue Behavior of Several Engineering Structural Alloys," International Metals Reviews, Vol. 30, No. 5, pp. 235-58.
4. Brinkman, C. R., 1985b, "Fatigue Behavior of Materials in Support of ASME Code Development," Pressure Vessel and Piping Technology 1985, A Decade of Progress, ASME, pp. 497-506.
5. Brinkman, C. R., Sikka, V. K., and King, R. T., April 1977, "Mechanical Properties of Liquid Metal Fast Breeder Reactor Primary Piping Materials," Nuclear Technology, Vol. 33, pp. 76-95.
6. Kaguchi, H., July 1998, personal communication, Mitsubishi Heavy Industries, Ltd., Kobe, Japan, 652-8585.
7. Kawasaki, N., July 1998, personal communication, The Japan Atomic Power Company, Chiyoda-ku, Tokyo 100, Japan.
8. Miura, M., Inagaki, T., and Kobayashi, T., "Present Status of DFBR Design in Japan," Proceedings of 4th Annual Scientific and Technical Conference of the Nuclear Society, Nuclear Energy and Human Safety (NE-93), June 28-July 2, 1993, Nizhni Novgorod, Russia.
9. Nishida, T., Ohno, K., Niinobe, S., Sukekawa, M., and Hirayama, H., "Elevated Temperature Properties and Micro Structure of 316FR," Proceedings of the 1993 Annual Meeting of JSME/MMD.
10. 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, ed. C. R. Brinkman and H. W. Garvin, pp. 124-41.
11. Schirra, M. and Heger, S., September 1990, "Zeitstandestigkeits-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.
12. Schirra, M., Heger, S., Ritter, M., de las Rivas, M., and Chamero, A., August 1991, "Untersachungen zum zeitstandfestigkeits-und Kriechverhalten am Austenitischen Stahl AISI 316-NET Abschlußbericht," KfK 4861, Kernforschungszentrum, Karlsruhe, Germany.
13. 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, Proceedings, ASME/PVP, 1995.