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Technical Paper

Fatigue Behavior of Type 316 Stainless Steel Irradiated in a Mixed Spectrum Fission Reactor Forming Helium

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Pages 538-547 | Published online: 12 May 2017

References

  • J. M. Beeston and C. R. Brinkman, “Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temper atures,” Irradiation Effects on Structural Alloys for Nuclear Reactor Applications, ASTM STP 484, p. 419, American Society for Testing and Materials (1970).
  • C. R. Brinkman and G. E. Korth, “Low Cycle Fatigue and Hold Time Comparisons of Irradiated and Unirradiated Type 316 Stainless Steel,” Met. Trans., 5, 792 (1974).
  • C. E. De Bogdan, “Tensile and Fatigue Data for Irradiated and Unirradiated AISI 319 Stainless Steel and Titanium-5 percent Aluminum-2.5 percent Tin: Application of the Method of Universal Slopes,” NASA TMX-2883, National Aeronautics and Space Administration (1973).
  • H. H. Smith and P. Shahinian, “Fatigue Behavior of Irradiated Thin-Section Type 348 Stainless Steel at 550°F (288°C),” Effects of Radiation on Substructure and Me chanical Properties of Metals and Alloys, ASTM STP 529, p. 451, American Society for Testing and Materials (1973).
  • K. L. Murty and J. R. Holland, “Low-Cycle Fatigue Characteristics of Irradiated 304 Stainless Steel,” Trans. Am. Nucl. Soc., 34, 185 (1980).
  • C. F. Serpan, Jr., H. H. Smith, F. A. Smidt, and A. G. Pieper, “Elevated-Temperature Fatigue Char acteristics of Helium-Implanted Stainless Steel,” Proc. Int. Mtg. Technology of Controlled Thermonuclear Fusion Experiments and the Engineering Aspects of Fusion Reactors, Austin, Texas, November 20–22, 1972, CONF-721111, p. 993, U.S. Atomic Energy Commission (1974).
  • Annual Book of ASTM Standards, Part 10, E606, American Society for Testing and Materials (1980).
  • W. D. Turner and M. Simon-Tov, “HEATING/3-An IBM 360 Heat Conduction Program,” ORNL/TM-3208, Oak Ridge National Laboratory (Feb. 1971).
  • J. E. Palnetine, “The Development of Silicon Carbide as a Routine Irradiation Temperature Monitor, and Its Calibration in a Thermal Reactor,” J. Nucl. Mater., 61, 243 (1976).
  • “Recommendations for Displacement Calculations for Reactor/Accelerator Studies in Austenite Steel,” Nucl. Eng. Des., 33, 91 (1975).
  • F. W. Wiffen et al., “The Production Rate of Helium During Irradiation of Nickel in Thermal Spectrum Fission Reactors,” J. Nucl. Mater. (1982, to be published).
  • J. B. Conway, R. H. Stentz, and J. T. Berling, “Fatigue, Tensile, and Relaxation Behavior of Stainless Steel”, p. 35, U.S. Atomic Energy Commission (1975).
  • S. S. Manson, Thermal Stress and Low-Cycle Fatigue, p. 160, McGraw-Hill Book Company, New York (1966).
  • C. W. Hunter, R. L. Fish, and J. J. Holmes, “Channel Fracture in Irradiated EBR-II Type 304 Stainless Steel,” Trans. Am. Nucl. Soc., 15, 254 (1972).
  • C. F. Serpan, Jr., D. J. Michel, H. H. Smith, and A. G. Pieper, “Microstructural Effects of Implanted Helium on Fatigue of 316 Stainless Steel,” Trans. Am. Nucl. Soc., 16, 71 (1973).
  • D. J. Michel, C. F. Serpan, Jr., and H. H. Smith, “Effect of Helium on the Fatigue Behavior of the Molybdenum-Base Alloy TZM at 900°C,” Nucl. Technol., 22, 79 (1974).
  • B. I. Sandor, Cyclic Stress and Strain, p. 149, The University of Wisconsin Press, Madison, Wisconsin (1972).
  • J. T. Berling and J. B. Conway, “A Proposed Method for Predicting the Low-Cycle Fatigue Behavior of 304 and 316 Stainless Steel,” Trans. Metal Soc. AIME, 245, 1137 (1969).
  • M. L. Grossbeck and P. J. Maziasz, “Tensile Properties of Type 316 Stainless Steel Irradiated in a Simulated Fusion Reactor Environment,” J. Nucl. Mater., 85 & 86, 883 (1979).
  • C. R. Brinkman, G. E. Korth, and J. M. Beeston, “Influence of Irradiation on the Creep/Fatigue Behavior of Several Austenitic Stainless Steels and Incoloy 800 at 700°C,” Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys, ASTM-STP-529, p. 473, American Society for Testing and Materials (1973).
  • M. L. Grossbeck, J. O. Stiegler, and J. J. Holmes, “Effects of Irradiation on the Fracture Behavior of Austenitic Stainless Steels,” Radiation Effects in Breeder Reactor Structural Materials, M. L. Bleiberg and J. W. Bennett, Eds., American Institute of Mining, Metallurgical, and Petroleum Engineers (1977).
  • J. D. Karston and J. C. Scully, “Fractographic Observations on the Stress Corrosion Cracking of Some Austenitic Stainless Steels in MgCl2 Solutions at 154°C,” Corros.-NACE, 26, 387 (1970).
  • HIDEYA Okada, YUZO Hosoi, and Seizaburo Abe, “Effect of Molybdenum on Stress Corrosion Cracking of Austenitic Stainless Steels,” Proc. Fifth Int. Congress on Metallic Corrosion, Tokyo, Japan, May 21–27, 1972, CONF-720523 (1974).
  • C. C. Baker and M. A. Abdou, Eds., “STARFIRE-A Commercial Fusion Tokamak Power Plant Study,” ANL/FPP-80-1, Argonne National Laboratory (1980).

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