Analysis of swelling behaviour of ferritic/martensitic steels

References

• G.R. Odette, On mechanisms controlling swelling in ferritic and martensitic alloys, J. Nucl. Mater. 155–157 (1988), pp. 921–927. doi: 10.1016/0022-3115(88)90442-4
   Web of Science ®Google Scholar
• D.J. Mazey, G.P. Walters, S.N. Buckley, S.M. Murphy, W. Hanks, and D.E.J. Bolster, Radiation damage simulation studies in the Harwell VEC of selected austenitic and ferritic alloys for fusion applications, J. Nucl. Mater. 155-157 (1988), pp. 891–895. doi: 10.1016/0022-3115(88)90436-9
   Web of Science ®Google Scholar
• E.A. Little and D.A. Stow, Void-swelling in irons and ferritic steels: II. An experimental survey of materials irradiated in a fast reactor, J. Nucl. Mater. 87 (1979), pp. 25–39. doi: 10.1016/0022-3115(79)90123-5
   Web of Science ®Google Scholar
• D.S. Gelles and L.E. Thomas, Effects of neutron irradiation on microstructure in experimental and commercial ferritic alloys, in Steels for use in Nuclear Energy Technologies, J.W. Davis and D.J. Michel, eds., The Metallurgical Society of AIME, Warrendale, PA, 1984, pp. 559–568.
   Google Scholar
• P.J. Maziasz, R.L. Klueh, and J.M. Vitek, Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR, J. Nucl. Mater. 141–143 (1986), pp. 929–937. doi: 10.1016/0022-3115(86)90120-0
   Web of Science ®Google Scholar
• L.L. Horton and L.K. Mansur, Experimental determination of the critical cavity radius in Fe-10Cr for ion irradiation, in Effects of Radiation on Materials: Twelfth International Symposium, ASTM STP 870,F.A. Garner and S.J. Perrin, eds., American Society for Testing and Materials, Philadelphia, PA, 1985, pp. 344–362.
   Google Scholar
• E.A. Little, R. Bullough, and M.H. Wood, On the swelling resistance of ferritic steel, Proc. Roy. Soc. Lond. A 372 (1980), pp. 565–579. doi: 10.1098/rspa.1980.0131
   Web of Science ®Google Scholar
• R. Bullough, M.H. Wood, and E.A. Little, A microstructural explanation for the low swelling of ferritic steels, in Effects of Radiation on Materials: Tenth Conference, ASTM STP 725, D. Kramer, H.R. Brager, and J.S. Perrin, eds., American Society for Testing and Materials, Philadelphia, PA, 1981, pp. 593–609.
   Google Scholar
• J.J. Sniegowski and W.G. Wolfer, On the physical basis for the swelling of ferritic steels, in Ferritic Alloys for Use in Nuclear Energy Technologies, J.W. Davis and D.J. Michel, eds., The Metallurgical Society of AIME, Warrendale, PA, 1984, pp. 579–586.
   Google Scholar
• T.S. Morgan, E.A. Little, R.G. Faulkner, and J.M. Ticthmarsh, Interfacial segregation in fast reactor irradiated 12% chromium martensitic steel, in Effects of Radiation on Materials: Fifteenth International Symposium, ASTM STP 1125, R.E. Stoller, A.S. Kumar, and D.S. Gelles, eds., American Society for Testing and Materials, Philadelphia, PA, 1985, pp. 633–644.
   Google Scholar
• L.K. Mansur and E.H. Lee, Theoretical basis for unified analysis of experimental data and design of swelling resistant alloys, J. Nucl. Mater. 179–181 (1991), pp. 105–110.
   Web of Science ®Google Scholar
• E.H. Lee and L.K. Mansur, Unified theoretical analysis of experimental swelling data for irradiated austenitic and ferritic/martensitic alloys, Metal. Trans. A 21 (1990), pp. 1021–1035. doi: 10.1007/BF02698235
   Web of Science ®Google Scholar
• E.A. Little, Microstructural evolution in irradiated ferritic-martensitic steels: transitions to high dose behaviour, J. Nucl. Mater. 206 (1993), pp. 324–334. doi: 10.1016/0022-3115(93)90131-H
   Web of Science ®Google Scholar
• J.J. Kai, G.L. Kulcinski, and R.A. Dodd, Microstructural evolution in helium doped HT-9 ferritic steel following 14 MeV nickel ion irradiation, J. Nucl. Mater. 141–143 (1986), pp. 731–737. doi: 10.1016/0022-3115(86)90082-6
   Web of Science ®Google Scholar
• E.A. Little, D.R. Arkell, D.R. Harries, G.R. Lewthwaite, and T.M. Williams, Development of ferritic-martensitic steels for fast-reactor applications, in Irradiation Behaviour of Metallic Materials for Fast Reactor Core Components, Vol. 1, J. Poirier and J.M. Dupouy, eds., CEA, Gif-Sur-Yvette, 1979, pp. 31–34.
   Google Scholar
• F.A. Garner, M.B. Toloczko, and B.H. Sencer, Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure, J. Nucl. Mater. 276 (2000), pp. 123–142. doi: 10.1016/S0022-3115(99)00225-1
   Web of Science ®Google Scholar
• F.A. Garner, Dimensional Stability – Swelling, in Reference Module Materials Science and Materials Engineering Comprehensive Nuclear Materials, 4 (2012), pp. 33–95.
   Google Scholar
• F.A. Garner and A.S. Kumar, The influence of both major and minor element composition on void swelling in austenitic steels, in Radiation-induced Changes in Microstructure, 13th International Symposium, Part 1, ASTM STP 955, F.A. Garner, N.H. Packan, and A.S. Kumar, eds., The Metallurgical Society of AIME, Philadelphia, PA, 1987, pp. 289–314.
   Google Scholar
• F.A. Garner, Overview of the swelling behaviour of 316 stainless steel, in Proceedings of the Symposium on Optimizing Materials for Nuclear Applications, F.A. Garner and D.S. Gelles, eds., The Metallurgical Society of AIME, Warrendale, PA, 1985, p. 111–139.
   Google Scholar
• F.A. Garner, Recent insights on the swelling and creep of irradiated austenitic alloys, J. Nucl. Mater. 122 (1984), pp. 459–471. doi: 10.1016/0022-3115(84)90641-X
   Web of Science ®Google Scholar
• F.A. Garner and M.B. Toloczko, High dose effects in neutron irradiated face-centered cubic metals, J. Nucl. Mater. 206 (1993), pp. 230–248. doi: 10.1016/0022-3115(93)90126-J
   Web of Science ®Google Scholar
• F.A. Garner, J.M. McCarthy, An assessment of Fe-Cr-Mn austenitic alloys for fusion service, in Reduced Activation Materials for Fusion Reactors, ASTM STP 1047, Klueh R.L., Gelles D.S., Packan N.H., Okada M., eds., American Society for Testing and Materials, Philadelphia, PA, 1990. pp. 19–29.
   Google Scholar
• F.A. Garner, H.R. Brager, D.S. Gelles, and J.M. McCarthy, The possible influence of order-disorder transformations on the swelling of 85Ni-15Cr nichrome alloy, J. Nucl. Mater. 148 (1987), pp. 294–301. doi: 10.1016/0022-3115(87)90023-7
   Web of Science ®Google Scholar
• M.B. Toloczko and F.A. Garner, Irradiation creep and void swelling of two LMR heats of HT9 at ∼ 400°C and 165 dpa, J. Nucl. Mater. 233-237 (1996), pp. 289–292. doi: 10.1016/S0022-3115(96)00413-8
   Web of Science ®Google Scholar
• M.B. Toloczko and F.A. Garner, Variability of irradiation creep and swelling of HT9 irradiated to high neutron fluence at 400-600°C, in Effects of Radiation on Materials, 18th International Symposium, ASTM STP 1325, R.K. Nanstad, M.L. Hamilton, F.A. Garner, and A.S. Kumar, eds., American Society for Testing and Materials, Philadelphia, PA, 1999, pp. 765–782.
   Google Scholar
• M.B. Toloczko, F.A. Garner, and C.R. Eiholzer, Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at ∼ 400°C, J. Nucl. Mater. 212–215 (1994), pp. 604–607. doi: 10.1016/0022-3115(94)90131-7
   Web of Science ®Google Scholar
• E.H. Lee and L.K. Mansur, Mechanisms of swelling suppression in cold-worked phosphorous-modified Fe-Ni-Cr alloys, Phil. Mag. A 61 (1990), pp. 733–749. doi: 10.1080/01418619008231945
   Google Scholar
• V.F. Sears, Kinetics of void growth in irradiated metals, J. Nucl. Mater. 39 (1971), pp. 18–26. doi: 10.1016/0022-3115(71)90179-6
   Web of Science ®Google Scholar
• L.K. Mansur, Theory and experimental background on dimensional changes in irradiated alloys, J. Nucl. Mater. 216 (1994), pp. 97–123. doi: 10.1016/0022-3115(94)90009-4
   Web of Science ®Google Scholar
• L.K. Mansur and W.A. Coghlan, Mechanisms of helium interaction with radiation effects in metals and alloys: a review, J Nucl Mater. 119 (1983), pp. 1–25. doi: 10.1016/0022-3115(83)90047-8
   Web of Science ®Google Scholar
• D.S. Gelles, Microstructural examination of commercial ferritic alloys at 200 dpa, J. Nucl. Mater. 233–237 (1996), pp. 293–298. doi: 10.1016/S0022-3115(96)00222-X
   Web of Science ®Google Scholar
• J.M. Vitek and R.L. Klueh, Microstructure of 9 Cr-1 MoVNb steel irradiated to 36 dpa at elevated temperatures in HFIR, J. Nucl. Mater. 122 (1984), pp. 254–259. doi: 10.1016/0022-3115(84)90606-8
   Web of Science ®Google Scholar
• J.M. Vitek, R.L. Klueh, Precipitation reactions during the heat treatment of ferritic steels Met. Trans. A, 14A (1983), pp. 1047–1055.
   Google Scholar
• P. Dubuisson, D. Gilbon and J.L. Séran, Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix, J. Nucl. Mater. 205 (1993), pp. 178–189. doi: 10.1016/0022-3115(93)90080-I
   Web of Science ®Google Scholar
• A.V. Povstyanko, A.Ye. Fedoseev, O.Yu. Makarov and V.I. Prokhorov, A study of four experimental fuel subassemblies using EP-450 ferritic-martensitic pin claddings and hexagonal ducts after irradiation to 108-163 dpa in the BOR-60 Reactor, Trans ANS 103 (2010), pp. 9–10.
   Google Scholar
• V.N. Voyevodin, O.V. Borodin, V.V. Bryk, A.S. Kalchenko, Y.E. Kupriyanova, A.V. Permyakov, and F.A. Garner, Comparison of ion-induced swelling of EP-450 and EP-450-ODS ferritic-martensitic alloys to very large dpa levels, PowerPoint Presentation, Private Communication, F.A. Garner, April 11, 2011.
   Google Scholar
• B.H. Sencer, J.R. Kennedy, J.I. Cole, S.A. Maloy, and F.A. Garner, Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155dpa at 443°C, J. Nucl. Mater. 393 (2009), pp. 235–241. doi: 10.1016/j.jnucmat.2009.06.010
   Web of Science ®Google Scholar
• R.L. Klueh, N. Hashimoto, M.A. Sokolov, P.J. Maziasz, K. Shiba, and S. Jitsukawa, Mechanical properties of neutron-irradiated nickel-containing martensitic steels: II. review and analysis of helium-effects studies, J. Nucl. Mater. 357 (2006), pp. 169–182. doi: 10.1016/j.jnucmat.2006.05.049
   Web of Science ®Google Scholar