Abstract
Chromium-molybdenum ferritic (martensitic) steels are leading candidates for the structural components for fusion reactors. However, irradiation of steels containing molybdenum or niobium in a fusion environment will produce long-lived radioactive isotopes that will lead to difficult waste disposal problems. To alleviate the waste disposal problem, ferritic steels are being developed that are analogous to conventional Cr-Mo steels, but with molybdenum replaced by tungsten and niobium replaced by tantalum. Experimental steels containing 0.1% C, 2 1/4 to 12% Cr, 0 to 2% W, 0 or 0.25% V, and 0 or 0.07% Ta were produced. Charpy impact properties were determined. A 5Cr-2W-0.25V steel and a 9Cr-2W-0.25V-0.07Ta steel had the best impact properties. The impact properties of these two steels as well as those of a 9Cr-2W-0.25V and a 12Cr-2W-0.25V steel were as good or better than the properties of similarly heat treated conventional 9Cr-1MoVNb and 12Cr-1MoVW steels.
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N.M. Ghoniem, A. Shabaik, and M.Z. Youssef:Ferritic Alloys for Use in Nuclear Energy Technologies, pp. 201–208, The Metallurgical Society of AIME, Warrendale, Pennsylvania, 1984.
D.S. Gelles and M.L. Hamilton:Alloy Development for Irradiation Performance Semiannu. Prog. Rep., September 30, 1984, DOE/ER-0045/13, U.S. Department of Energy, Washington, DC, March 1985.
R.L. Klueh and E.E. Bloom:Alloy Development for Fast Induced Radioactivity Decay for Fusion Reactor Applications, ORNL/TM-8894, Oak Ridge National Laboratory, Oak Ridge, Tennessee, March 1984.
R.W. Honeycombe:Structure and Strength of Alloy Steels, Climax Molybdenum Company, London, 1974.
R.L. Klueh and P.J. Maziasz:Met. Trans., in press.
R.L. Klueh:Met. Trans., in press.
J.M. Vitek and R.L. Klueh:Met. Trans., 1983, vol. 14A, pp. 1047–1055.
F.A. Smidt, Jr., J.R. Hawthorne, and V. Provenzano:Effects of Radiation on Materials, ASTM STP 725, American Society for Testing and Materials, Philadelphia, 1981, pp. 264–269.
J.M. Vitek, W.R. Corwin, R.L. Klueh, and J.R. Hawthorne,J. Nucl. Mater., 1986, vols. 141–143, pp. 948–953.
W.R. Corwin and A.M. Hougland:The Use of Small Scale Specimens for Testing Irradiated Material, ASTM STP 888, American Society for Testing and Materials, Philadelphia, 1986, pp. 325–338.
K. Anderko, K. David, W. Ohly, M. Schirra, and C. Wassilew:Ferritic Alloys for use in Nuclear Energy Technologies, The Metallurgical Society of AIME, Warrendale, Pennsylvania, 1984, pp. 299–306.
B.A. Chin and R.C. Wilcox:Ferritic Alloys for use in Nuclear Energy Technologies, The Metallurgical Society of AIME, Warrendale, Pennsylvania, pp. 347–356.
Y. Hosoi, N. Wade, T. Urita, M. Tannino, and H. Komatsu:J. Nucl. Mater., vols. 133 and 134, pp. 337–342.
Y. Hosoi, N. Wade, S. Kunimitsu, and T. Urita:J. Nucl. Mater., 1986, vol. 141–143, pp. 461–467.
N. Igata:J. Nucl. Mater., 1985, vols. 133 and 134, pp. 141–148.
F.B. Pickering:Physical Metallurgy and the Design of Steels, Applied Science Publishers, Ltd., London, 1978.
D.A. Canonico: Private Communication, 1987.
R.L. Klueh:Martensitic Transformations (COMAT), Japan Institute of Metals, Sendai, Japan, 1987, pp. 601–606.
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Research sponsored by the Office of Fusion Energy, U.S. Department of Energy, under contract DE-AC05-84OR21400 with the Martin Marietta Energy Systems, Inc.
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Klueh, R.L., Corwin, W.R. Impact behavior of Cr-W steels. J. Materials Engineering 11, 169–175 (1989). https://doi.org/10.1007/BF02834465
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DOI: https://doi.org/10.1007/BF02834465