Abstract
Ferritic and martensitic steels are finding increased application for structural components in several reactor systems. Low-alloy steels have long been used for pressure vessels in light water fission reactors. Martensitic stainless steels are finding increasing usage in liquid metal fast breeder reactors and are being considered for fusion reactor applications when such systems become commercially viable. Recent efforts have evaluated the applicability of oxide dispersion-strengthened ferritic steels. Experiments on the effect of irradiation on these steels provide several examples where contributions are being made to materials science and engineering. Examples are given demonstrating improvements in basic understanding, small specimen test procedure development, and alloy development.
Similar content being viewed by others
References
C. Cawthorne and E.J. Fulton:Nature, 1967, vol. 216, p. 515.
J.L. Straalsund, H.R. Brager, and J.J. Holmes: inRadiation- Induced Voids in Metals, CONF-710601, Atomic Energy Commission, Office of Information Services, government publication, Apr. 1972, pp. 142–55.
J.J. Laidler, J.J. Holmes, and J.W. Bennett: inRadiation Effects in Breeder Reactor Structural Materials, M.L. Bleiberg and J.W. Bennett, eds., TMS-AIME, New York, NY, 1977, pp. 41–52.
S.D. Harkness, B.J. Kestel, and P. Okamoto: inRadiation Effects in Breeder Reactor Structural Materials, M.L. Bleiberg and J.W. Bennett, eds., TMS-AIME, New York, NY, 1977, pp. 334–37.
F.A. Garner, H.R. Brager, and R.J. Puigh:J. Nucl. Mater., 1985, vol. 133–134, pp. 535–39.
J.L. Seran, L. Le Naour, P. Grosjean, N.P. Higon, Y. Carteret, and A. Maillard: inEffects of Radiation on Materials, 12th Int. Symp., F.A. Garner and J.S. Perrin, eds., ASTM STP 870, ASTM, Philadelphia, PA, 1985, pp. 233–47.
R.J. Puigh and F.A. Garner: inRadiation-Induced Changes in Microstructure, 13th Int. Symp. (Part 1), F.A. Garner, N.H. Packan, and A.S. Kumar, eds., ASTM STP 955, ASTM, Philadelphia, PA, 1987, pp. 154–60.
R. Bajaj, R.P. Shogan, C. DeFlitch, R.L. Fish, M.M. Paxton, and M.L. Bleiberg: inEffects of Radiation on Materials, 10th Conf, D. Kramer, H.R. Brager, and J.S. Perrin, eds., ASTM STP 725, ASTM, Philadelphia, PA, 1981, pp. 326–51.
W.J.S. Yang, D.S. Gelles, J.L. Straalsund, and R. Bajaj:J. Nucl. Mater., 1985, vol. 132, pp. 249–65.
Sandvik HT-9 data sheet S-l, 720-ENG, Sandviken, Sweden, May 1981.
V.K. Sikka: inProc. Top. Conf. on Ferritic Alloys for Use in Nuclear Energy Technologies, TMS-AIME, Warrendale, PA, 1984, pp. 317–27.
A.J. Lovell, A.L. Fox, W.H. Sutherland, and S.L. Hecht: inInt. Conf. on Reliable Fuels for Liquid Metal Reactors, American Nuclear Society, La Grange Park, IL, 1987, pp. 3–25-3–36.
F.E. Tippets, L.N. Salemo, CE. Boardman, W. Kwant, R.E. Murata, and C.R. Snyder:Proc. Am. Power Conf., 1987, vol. 49, pp. 874–83; S. Vaidyanathan and R.E. Murata: inProc. Int. Conf. on Reliable Fuels for Liquid Metal Reactors, American Nuclear Society, La Grange Park, IL, 1987, pp. 1-43–1-60.
D.S. Bost and L.D. Feiten: inInt. Conf. on Reliable Fuels for Liquid Metal Reactors, American Nuclear Society, La Grange Park, IL, 1987, pp. 1–61-1–68.
The Fusion Reactor Materials Program Plan, Section 1, Alloy Development for Irradiation Performance, DOE/ET-0032/1, July 1978.
Alloy Development for Irradiation Performance Quarterly Progress Reports (beginning with the period ending Dec. 31, 1979), DOE/ ER-0045/1-16.
S.N. Rosenwasser, P. Miller, J.A. Dalessandro, J.M. Rawls, W.E. Toffolo, and W. Chen:J. Nucl. Mater., 1979, vol. 85–86, pp. 177–82.
H. Attaya, G.L. Kulcinski, and W.G. Wolfer:J. Nucl. Mater., 1984, vol. 122–123, pp. 96–100.
Starfire, A Commercial Tokamak Fusion Power Plant Study, ANL/ FPP-80-1, Sept. 1980, vol. 1, pp. 10–232.
A Demonstration Tokamak Power Plant Study, ANL/FPP/82-1, Sept. 1982, pp. 2–3.
MARS Mirror Advanced Reactor Study, Final Report, UCRL- 53480, July 1984, vol. 1-B, pp. 12-9–12-24.
Blanket Comparison and Selection Study, Final Report, ANL/ FPP-84-1, Sept. 1984, pp. 7.3–4.
Modeling, Analysis & Experiments for Fusion Nuclear Technology, FNT Progress Report: Modeling and FINESSE, Jan. 1987, p. 1021.
J.L. Straalsund and D.S. Gelles: inProc. Top. Conf. on Ferritic Alloys for Use in Nuclear Energy Technologies, TMS-AIME, Warrendale, PA, 1984, HEDL-SA-2771, May 1983.
D.S. Gelles:J. Nucl. Mater., 1987, vol. 149, pp. 192–99.
D.S. Gelles and R.L. Meinecke Ermi: inAlloy Development for Irradiation Performance Semiannual Progress Report for the period ending September 30, 1983, DOE/ER-0045/11 (1983), pp. 103–07.
F.A. Garner and D.S. Gelles:Fusion Reactor Materials, DOE/ ER/0313/5, Sept. 1988, PNL-SA-15471, pp. 179–87.
G.R. Odette:Fusion Reactor Materials, DOE/ER-0313/4, Sept. 1987, pp. 106–14.
J.J. Sniegowski and W.G. Wolfer: inProc. Top. Conf. on Ferritic Alloys for Use in Nuclear Energy Technologies, TMS-AIME, Warrendale, PA, 1984, pp. 579–91.
R. Bullough, M.H. Wood, and E.A. Little: inEffects of Radiation on Materials, 10th Conf, D. Kramer, H.R. Brager, and J.S. Perrin, eds., ASTM STP 725, ASTM, Philadelphia, PA, 1981, pp. 593–609.
D.S. Gelles:J. Nucl. Mater., 1982, vol. 108–109, pp. 515–26.
L.L. Horton and L.K. Mansur: inEffects of Radiation on Materials, 12th Int. Symp., F.A. Garner and J.S. Perrin, eds., ASTM STP 870, ASTM, Philadelphia, PA, 1985, pp. 344–62.
W.A. Coghlan and D.S. Gelles:Fusion Reactor Materials, DOE/ ER-0313/2, Mar. 1987, pp. 88–98.
Workshop on Solute Segregation and Phase Stability During Irradiation:J. Nucl. Mater., 1979, vol. 83.
S. Ohnuki, H. Takahashi, and T. Takeyama:J. Nucl. Mater., 1981, vol. 103–104, pp. 1121–26.
S. Ohnuki, H. Takahashi, and T. Takeyama:J. Nucl. Mater., 1984, vol. 122–123, pp. 317–21.
T. Muroga, A. Yamaguchi, and N. Yoshida: inEffects of Radiation on Materials: 14th Int. Symp., ASTM STP 1046, N.H. Packan, R.E. Stoller, and A.S. Kumar, eds., American Society for Testing and Materials, Philadelphia, PA, 1990, in press.
D.S. Gelles: inEffects of Radiation on Materials: 14th Int. Symp., ASTM STP 1046, N.H. Packan, R.E. Stoller, and A.S. Kumar, eds., American Society for Testing and Materials, Philadelphia, PA, 1990, pp. 73–97.
T.A. Lechtenberg: GA Technologies, San Diego, CA, unpublished work.
P. Chen and R.C. Wilcox: inEffects of Radiation on Materials: 14th Int. Symp., ASTM STP 1046, N.H. Packan, R.E. Stoller, and A.S. Kumar, eds., American Society for Testing and Materials, Philadelphia, PA, 1990, in press.
R.D. Griffin, R.A. Dodd, G.L. Kulcinski, and D.S. Gelles:Metall. Trans. A, in press.
D.S. Gelles and L.E. Thomas: inProc. Top. Conf. on Ferritic Alloys for Use in Nuclear Energy Technologies, TMS-AIME, Warrendale, PA, 1984, pp. 559–68.
P.J. Maziasz: inMaterials for Nuclear Reactor Core Applications, British Nuclear Energy Society, London, 1987, pp. 61–71.
P.J. Maziasz, R.L. Klueh, and J.M. Vitek:J. Nucl. Mater., 1986, vol. 141–143, pp. 929–37.
The Use of Small-Scale Specimens for Testing Irradiated Material, W.R. Corwin and G.E. Lucas, eds., ASTM STP 888, ASTM, Philadelphia, PA, 1986.
B.S. Louden, A.S. Kumar, F.A. Garner, M.L. Hamilton, and W.L. Hu:J. Nucl. Mater., 1988, vols. 155–157, pp. 662–67.
F.H. Huang: inThe Use of Small-Scale Specimens for Testing Irradiated Material, W.R. Corwin and G.E. Lucas, eds., ASTM STP 888, ASTM, Philadelphia, PA, 1986, pp. 290–304.
F.H. Huang:J. Test. Eval., 1985, vol. 13, pp. 257–64.
G.C. Bodine and R.E. McDonald: inFerritic Steels for High-Temperature Applications, A.K. Khare, ed., ASM, Metals Park, OH, 1983, pp. 9–20.
K. Hashimoto, M. Yamanaka, Y. Otoguro, T. Zaizen, M. Onayama, and T. Fujita: inProc. Top. Conf. on Ferritic Alloys for Use in Nuclear Energy Technologies, TMS-AIME, Warrendale, PA, 1984, pp. 307–15.
Report of the DOE Panel on Low Activation Materials for Fusion Applications, R.W. Conn, Panel Chairman, UCLA/PPG-728, June 1983.
R.L. Klueh, D.S. Gelles, and T.A. Lechtenberg:J. Nucl. Mater., 1986, vol. 141–143, pp. 1081–87.
D.S. Gelles: in Proc.14th ASTM Int. Symp. on Effects of Radiation on Materials, Andover, MA, June 1988, in press.
J.J. Fischer: U.S. Patent 4,075,010, Feb. 21, 1978.
Frontiers of High Temperature Materials II, J.S. Benjamin and R.C. Benn, eds., International Nickel Company, Huntington, WV, 1985.
R.W. Powell, G.D. Johnson, M.L. Hamilton, and F.A. Garner: inProc. Int. Conf. on Reliable Fuels for Liquid Metal Reactors, American Nuclear Society, La Grange Park, IL, 1987, pp. 4–17-4–29.
Author information
Authors and Affiliations
Additional information
This paper is based on a presentation made in the symposium “Irradiation-Enhanced Materials Science and Engineering” presented as part of the ASM INTERNATIONAL 75th Anniversary celebration at the 1988 World Materials Congress in Chicago, IL, September 25–29, 1988, under the auspices of the Nuclear Materials Committee of TMS-AIME and ASM-MSD.
Rights and permissions
About this article
Cite this article
Gelles, D.S. Contributions from research on irradiated ferritic/martensitic steels to materials science and engineering. Metall Trans A 21, 1065–1071 (1990). https://doi.org/10.1007/BF02698238
Issue Date:
DOI: https://doi.org/10.1007/BF02698238