Mechanical Properties of Ferritic Martenstic Steels: A Review

Open access

Abstract

The word-wide demand for energy is constantly increasing, and therefore ideas around future energy-generation are also on the increase with the aim of meeting this demand. This includes designs for the next generation of nuclear power reactors, such as gas-cooled, liquid-metal-cooled and water-cooled reactors; the goal being to create smarter ways to produce more economical, environmentally-friendly energy. The conditions such reactors would need to meet, present significant design challenges for scientist and engineers, not least around the structural materials and components to use. Depending on the operational conditions, use of elevated- temperature ferritic/martensitic materials such as P91 and P92 steel are favoured by several of the designs for use with out-of-core and in-core applications. The main goal behind this review article is to explain mechanical properties of P91 and P92 steel; these are two types of ferritic/martensitic steels. This reviewer, highlight and discuss the development of ferritic/martenisitc steels for nuclear programmes and to explain the effect of irradiation on mechanical properties of P91 and P92.

If the inline PDF is not rendering correctly, you can download the PDF file here.

  • [1] Smith R. Fast reactor progress—slow but sure Progress in Nuclear Energy. 1987 vol. 20 2 pp. 71-88.

  • [2] Kittel J. Frost B. Mustelier J. Bagley K. Crittenden G. and Van Dievoet J. History of fast reactor fuel development Journal of nuclear materials. 1993 vol. 204 pp. 1-13.

  • [3] Klueh R. and Nelson A. Ferritic/martensitic steels for next-generation reactors Journal of Nuclear Materials. 2007 vol. 371 1-3 pp. 37-52.

  • [4] Raj B. and Vijayalakshmi M. Ferritic steels and advanced ferritic–martensitic steels Comprehensive Nuclear Materials. 2012 vol. 4 pp. 97-121.

  • [5] Klueh R. Gelles D. and Lechtenberg T. Development of ferritic steels for reduced activation: the US program Journal of Nuclear Materials. 1986 vol. 141 pp. 1081-1087.

  • [6] Klueh R. and Harries D. High Chromium Ferritic and Martensitic Steels for Nuclear Applications. West Conshohocken PA : ASTM International.: 2001; p 221.

  • [7] Klueh R. Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors International Materials Reviews. 2005 vol. 50 5 pp. 287-310.

  • [8] Klueh R. Hashimoto N. and Maziasz P. Development of new nano-particle-strengthened martensitic steels Scripta Materialia. 2005 vol. 53 3 pp. 275-280.

  • [9] Klueh R. Ehrlich K. and Abe F. Ferritic/martensitic steels: promises and problems Journal of nuclear materials. 1992 vol. 191 pp. 116-124.

  • [10] Conn R. Bloom E. Davis J. Gold R. Little R. Schultz K. Smith D. and Wiffen F. Panel report on low activation materials for fusion applications Journal of Nuclear Materials. 1983 vol. 122 pp. 17–26.

  • [11] Chen-Yih H. and Lechtenberg T. A. Microstructure and mechanical properties of unirradiated low activation ferritic steel Journal of Nuclear Materials. 1986 vol. 141 pp. 1107-1112.

  • [12] Dulieu D. Tupholme K. and Butterworth G. Development of low-activation martensitic stainless steels Journal of Nuclear Materials. 1986 vol. 141 pp. 1097-1101.

  • [13] Kayano H. Kimura A. Narui M. Kikuchi T. and Ohta S. Effects of small changes in alloy composition on the mechanical properties of low activation 9% Cr-2% W steel Journal of nuclear materials. 1991 vol. 179 pp. 671-674.

  • [14] Abson D. Rothwell J. and Cane B. In Advances in welded creep resistant 9–12% Cr steels Proc. 5th Int. EPRI Conf. on ‘Advances in materials technology for fossil power plants 2007; 2007.

  • [15] Baral J. Creep characterization of Boron added P91 steel in the temperature range 600-650 degree C. National Metallurgical Laboratory (NML) 2011.

  • [16] Blum R. Hald J. Bendick W. Rosselet A. Vaillant J. Fynsvaerket O. Elsam F. and Mannesmann Forschungsinstitut D. Newly developed high-temperature-resistant ferritic-martensitic steels from the USA Japan and Europe. Neuentwicklungen hochwarmfester ferritischmartensitischer Staehle aus den USA Japan und Europa VGB Kraftwerkstechnik. 1994 vol. 74 (8) pp. 641-652.

  • [17] Canonico D. Thick-walled pressure vessels for energy systems Ferritic Steels for High-Temperature Applications. 1981 vol. pp. 31-41.

  • [18] Sikka V. Ward C. and Thomas K. Modified 9 Cr--1 Mo Steel--an Improved Alloy for Steam Generator Application Ferritic Steels for High-Temperature Applications. 1981 vol. pp. 65-84.

  • [19] Von Hagen I. and Bendick W. In Creep resistant ferritic steels for power plants International Symposium on Niobium 2001 2001; 2001; pp 753-776.

  • [20] Viswanathan R. and Nutting J. Advanced heat resistant steels for power generation. IOM Communications: 1999.

  • [21] Was G. S. Fundamentals of radiation materials science: metals and alloys. Springer: 2016.

  • [22] Little E. A. and Stoter L. Effects of Irradiation on Materials: Eleventh Conference ASTM STP 782 eds HR Brager and JS Perrin American Society for Testing and Materials Philadelphia. 1982 vol. pp. 207-233.

  • [23] Kohyama A. Hishinuma A. Gelles D. Klueh R. Dietz W. and Ehrlich K. Low-activation ferritic and martensitic steels for fusion application Journal of Nuclear Materials. 1996 vol. 233 pp. 138-147.

  • [24] Zinkle S. 1.03-Radiation-Induced effects on microstructure Comprehensive Nuclear Materials. 2012 vol. 1 pp. 65-98.

  • [25] Grossbeck M. L. Effect of radiation on strength and ductility of metals and alloys Comprehensive Nuclear Materials. 2012 vol. 1 pp. 99-122.

  • [26] Zinkle S. J. and Was G. Materials challenges in nuclear energy Acta Materialia. 2013 vol. 61 3 pp. 735-758.

Search
Journal information
Metrics
All Time Past Year Past 30 Days
Abstract Views 0 0 0
Full Text Views 156 156 25
PDF Downloads 119 119 13