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Technical Paper

Fatigue-Crack Propagation in Fast-Neutron-Irradiated Types-304 and -316 Stainless Steels

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Pages 148-155 | Published online: 12 May 2017

REFERENCES

  • L. A. JAMES and E. B. SCHWENK, Jr., “Fatigue Crack Propagation Behavior of Type 304 Stainless Steel at Elevated Temperatures,” Met. Trans., 2, 2, 491 (1971).
  • P. SHAHINIAN, H. H. SMITH, and H. E. WATSON, “Fatigue Crack Growth in Type 316 Stainless Steel at High Temperature,” J. Eng. Ind., Trans. ASME, Series B, 93. 4, 976 (1971).
  • L. A. JAMES, “The Effect of Elevated Temperature Upon the Fatigue Crack Propagation Behavior of Two Austenitic Stainless Steels,” Mechanical Behavior of Materials, III, 341, The Society of Materials Science, Japan (1972).
  • L. A. JAMES, “Fatigue Crack Growth in 20% Cold Worked Type 316 Stainless Steel at Elevated Temperatures,” Nucl. Technol., 16, 1, 316 (1972).
  • P. SHAHINIAN, H. E. WATSON, and H. H. SMITH, “Fatigue Crack Growth in Selected Alloys for Reactor Applications,” J. Mater., 7, 4, 527 (1972).
  • P. SHAHINIAN, H. H. SMITH, and H. E. WATSON, “Fatigue Crack Growth Characteristics of Several Austenitic Stainless Steels at High Temperatures,” Fatigue at Elevated Temperatures, ASTM STP-520, American Society for Testing and Materials, in press.
  • L. A. JAMES, “The Effect of Frequency Upon the Fatigue Crack Growth of Type 304 Stainless Steel at 1000° F,” Stress Analysis and Growth of Cracks, ASTM STP-513, pp. 218–229, American Society for Testing and Materials (1972).
  • L. A. JAMES, “Hold Time Effects on the Elevated Temperature Fatigue Crack Propagation of Type 304 Stainless Steel,” Nucl. Technol., 16, 3, 521 (1972).
  • L. A. JAMES, “The Effect of Stress Ratio on the Elevated Temperature Fatigue Crack Propagation of Type 304 Stainless Steel,” Nucl. Technol., 14, 2, 163 (1972).
  • K. R. WHEELER and L. A. JAMES, “Fatigue Behavior of Type 316 Stainless Steel Under Simulated Body Conditions,” J. Biomed. Mater. Res., 5, 3, 267 (1971).
  • L. A. JAMES, “Effect of Thermal Aging Upon the Fatigue Crack Propagation Behavior of Austenitic Stainless Steels,” to be published.
  • P. SHAHINIAN, H. H. SMITH, and J. R. HAWTHORNE, “Fatigue Crack Propagation in Stainless Steel Weldments at High Temperatures,” Welding J. Res. Suppl., 51, 11, 527s (1972).
  • L. A. JAMES, “Fatigue-Crack Growth in Type 304 Stainless Steel Weldments at Elevated Temperature,” J. Test. Eυal., 8, 1, 52 (1973).
  • L. A. JAMES, “Crack Propagation Behavior in Type 304 Stainless Steel Weldments at Elevated Temperature,” Welding J. Res. Suppl., 52, 4, 173s (1973).
  • L. A. JAMES, “Some Preliminary Observations on the Extension of Cracks Under Static Loadings at Elevated Temperature,” Intern. J. Fracture Mech., 8, 3, 347 (1972).
  • P. SHAHINIAN, H. E. WATSON, and H. H. SMITH, “Effect of Neutron Irradiation on Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperature,” ASTM Sixth International Symposium on Effects of Radiation on Structural Materials, Los Angeles, June 1972.
  • P. SHAHINIAN, H. E. WATSON, and H. H. SMITH, “Fatigue Crack Propagation in Neutron Irradiated Stainless Steel Weldments,” Irradiation Effects an Reactor Structural Materials, Quarterly-Progress Report, NRL Memorandum Report 2531, p. 18, U.S. Naval Research Laboratory (November 1972).
  • H. E. WATSON, L. E. STEELE, and P. SHAHINIAN, “Effects of Irradiation and Temperature on the Fatigue Properties of A533-B Steel,” Irradiation Effects on Reactor Structural Materials, Quarterly Progress Report, NRL Memorandum Report 2328, p. 12, U.S. Naval Research Laboratory (August 1971).
  • L. A. JAMES and J. A. WILLIAMS, “The Effect of Temperature and Neutron Irradiation Upon the Fatigue Crack Propagation Behavior of ASTM A533-B Steel,” J. Nucl. Mater., 47, 1, 17 (1973).
  • D. O. LEESER and J. E. KEMME, “Fatigue Tests on Irradiated and Control Specimens of Type 304 Stainless Steel, Zirconium, and a Tin-Zirconium Alloy,” CF-53-3-276, Part II (Del), p. 302, U.S. Atomic Energy Commission (1953).
  • C. N. SPALARIS, “Finding a Corrosion-Resistant Cladding for Superheater Fuels,” Nucleonics, 21, 9, 41 (1963).
  • M. KANGILASKI and F. R. SHOBER, “Correlation of Tensile and Fatigue Properties of Irradiated Type 347 Stainless Steel at Room Temperature,” Nucl. Appl., 5, 10, 283 (1968).
  • J. MOTEFF, J. P. SMITH, and W. J. STAPP, “Effects of Neutron Irradiation on the Plastic Fatigue Properties of Stainless Steel,” Trans. Am. Nucl. Soc., 12, 2, 585 (1969).
  • J. M. BEESTON and C. R. BRINKMAN, “Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures,” Irradiation Effects on Structural Alloys for Nuclear Reactor Applications, ASTM STP-484, p. 419, American Society for Testing Materials (1970).
  • J. B. CONWAY, J. T. BERLING, and R. H. STENTZ, “New Correlations Involving the Low-Cycle Fatigue and Short-Term Tensile Behavior of Irradiated and Unirradiated 304 and 316 Stainless Steel,” Nucl. Appl. Technol., 9, 1, 31 (1970).
  • C. R. BRINKMAN, G. E. KORTH, and R. R. HOBBINS, “Estimates of Creep Fatigue Interaction in Irradiated and Unirradiated Austenitic Stainless Steels,” Nucl. Technol., 16, 1, 297 (1972).
  • C. R. BRINKMAN, G. E. KORTH, and J. M. BEESTON, “The Influence of Irradiation on the Creep Fatigue Behavior of Several Austenitic Stainless Steels and Incoloy 800 at 700°C,” submitted to ASTM for publication in a forthcoming STP.
  • G. H. BROOMFIELD, J. GRAVENOR, J. MOFFAT, and E. E. C. HUTCHINS, “Effects of Neutron Irradiation on the Low Cycle Fatigue of 20–25–Nb Steel,” presented at BNES Conference on Irradiation Embrittlement and Creep in Fuel Cladding and Core Components, London, November 1972.
  • C. Z. SERPAN, Jr., H. H. SMITH, and A. G. PIEPER, “Effect of Cyclotron-Injected Helium on Fatigue Characteristics of Stainless Steel,” Trans. Am. Nucl. Soc., 15, 1, 251 (1972).
  • C. Z. SERPAN, Jr., H. H. SMITH, and A. G. PIEPER, “Fatigue Crack Growth in Helium-Implanted, Annealed and Cold Worked Type 316 Stainless Steel,” Trans. Am. Nucl. Soc., 15, 2, 721 (1972).
  • T. T. CLAUDSON, R. W. BARKER, and R. L. FISH, “The Effects of Fast Flux Irradiation on the. Mechanical Properties and Dimensional Stability of Stainless Steel,” Nucl. Appl. Technol., 9, 1, 10 (1970).
  • R. L. FISH, A. J. LOVELL, H. R. BRAGER, and J. J. HOLMES, “Tensile and Creep Behavior of Cold Worked Type 316 Stainless Steel After EBR-II Irradiation,” presented at BNES Conference on Irradiation Embrittlement and Creep in Fuel Cladding and Core Components, London, November 1972.
  • “Plane-Strain Fracture Toughness of Metallic Materials,” Specification E399-72, 1972 Annual Book of ASTM Standards, Part 31, p. 955, American Society for Testing and Materials (1972).
  • W. K. WILSON, “Stress Intensity Factors for Deep Cracks in Bending and Compact Tension Specimens,” Eng. Fracture Mech., 2, 2, 169 (1970).
  • P. PARIS and F. ERDOGAN, “A Critical Analysis of Crack Propagation Laws,” J. Basic Eng., Trans. ASME, Series D, 85, 4, 528 (1963).
  • W. R. MARTIN and J. R. WEIR, “The Effect of Irradiation Temperature on the Postirradiation Stress-Strain Behavior of Stainless Steel,” Flow and Fracture of Metals and Alloys in Nuclear Environments, ASTM STP-380, p. 251, American Society for Testing Mate–rials (1965).
  • E. E. BLOOM and J. O. STEIGLER, “Effect of Fast Neutron Irradiation on the Creep Rupture Properties of Type 304 Stainless Steel at 600°C,” Irradiation Effects on Structural Alloys for Nuclear Reactor Application, ASTM STP–484, p. 451, American Society for Testing Materials (1970).
  • A. J. LOVELL, “Postirradiation Creep of Annealed Type 316 Stainless Steel,” Nucl. Technol., 16, 1, 323 (1972).
  • L. A. JAMES, “The Effect of Temperature Upon the Fatigue-Crack Growth Behavior of Two Nickel-Base Alloys,” J. Eng. Mater. Technol., in press.

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