Abstract
Design concepts for the next generation of nuclear power reactors include water-cooled, gas-cooled, and liquid-metal-cooled reactors. Reactor conditions for several designs offer challenges for engineers and designers concerning which structural and cladding materials to use. Depending on operating conditions, some designs favor elevated-temperature ferritic/martensitic steels for in-core and out-of core applications. Such steels have been investigated in previous work on international fast reactor and fusion reactor research programs. Steels from these fission and fusion programs will provide reference materials for future fission applications. In addition, new elevated-temperature steels have been developed in recent years for conventional power systems that also need to be considered.
Similar content being viewed by others
References
A technology roadmap for generation IV nuclear energy systems, GIF-002-00, U.S. DOE nuclear energy research advisory committee and the Generation IV International Forum, December 2002.
Nanstad R K, Pressure vessel and piping materials for light-water reactors, In Bever M B, editor, Encyclopedia of materials science and engineering, New York: Pergamon Press; (1986) 3928.
Conn R W, Bloom E E, Davis J W, Gold R E, Little R, Schultz K R, Smith D L and Wiffen F W, Panel report on low activation materials for fusion applications, Nucl Tech/Fusion, 5 (1984) 291.
Klueh R L and Harries D R, High-chromium ferritic and martensitic steels for nuclear applications, West Conshohocken, Pennsylvania, American Society for Testing and Materials, (2001).
Masuyama F, New development in steels for power generation boilers, in Advanced heat resistant steel for power generation, Viswanathan R, Nutting J, editors, London: Institute of Materials; (1999) 33.
Klueh R L, Bloom E E, The development of ferritic steels for fast induced-radioactivity decay for fusion reactor applications, Nucl. Eng. & Design/Fusion, 2 (1985) 383.
Klueh R L, Reduced-Activation steels: Future development for improved creep strength, J. Nucl. Mater, 378 (2008) 159.
Hättestrand M, Schwind M, Andrén H.-O, Microanalysis of 9–12% chromium steels P92 and P122, in Advanced heat resistant steel for power generation, Viswanathan R, Nutting J, editors, London: Institute of Materials; (1999) 199.
Klueh R L, Evans N D, Maziasz P J, and Sikka V K, Creeprupture behavior of 3Cr-3W-V bainitic steels, Intl. J. Press. Vessels and Piping 84 (2007) 29.
Sikka V K, Klueh R L, Maziasz P J, Babu S, Santella M, Jawad M H, Paules J R and Orie K E, Mechanical properties of new grades of Fe-3Cr-W alloys, in experience with creep-strength enhanced ferritic steels and new and emerging computational methods, PVP, New York: American Society Mechanical Engineers; 476 (2004) 97.
Ukai S, Fujiwara M, Perspective of ODS alloys application in nuclear environments, J. Nucl. Mater., 307–311 (2002) 749.
Klueh R L, Hashimoto N, and Maziasz P J, Development of new nano-particle-strengthened martensitic steels, Scripta Mat. 53 (2005) 275.
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Klueh, R.L. Ferritic/martensitic steels for advanced nuclear reactors. Trans Indian Inst Met 62, 81–87 (2009). https://doi.org/10.1007/s12666-009-0011-3
Received:
Revised:
Accepted:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s12666-009-0011-3