Abstract
Advanced fission-based reactors challenge our ability to fully understand environment–materials reactions in terms of fundamental stability and kinetics, including the influences of composition, microstructure, and system design, and to predict associated long-term performance. This article briefly describes corrosion reactions and the processes by which such are managed for several elevated-temperature environments associated with advanced reactor concepts: helium, molten Pb–Bi, fluorides, and supercritical water. For most of the subject environments, corrosion resistance critically depends on the ability to form and maintain protective surface layers. Effects of corrosion on mechanical behavior can be from thermally and chemically induced changes in microstructures or from environmental effects on cracking susceptibility. In most cases, the simultaneous effects of chemical reactivity and radiation have not been fully addressed, nor has much attention been paid to newly emerging alloy compositions or the effects of substantially increased operating temperatures.
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H. Burlet, J.M. Gentzbittel, C. Cabet, P. Lamagnère, M. Blat, D. Renaud, S. Dubiez-Le Goff, D Pierron, “Evaluation of Nickel-Based Materials for VHTR Heat Exchanger,” in Structural Materials for Innovative Nuclear Systems (SMINS) (OECD Publishing, London, 2008). p. 79.
W. J. Quadakkers, Werkst. Korros. 36, 335 (1985).
C. Cabet, J. Chapovaloff, F. Rouillard, G. Girardin, D. Kaczorowski, K. Wolski, M. Pijolat, J. Nucl. Mater. 375, 173 (2008).
F. Rouillard, C. Cabet, K. Wolski, M. Pijolat, Oxid. Met. 68, 133 (2007).
C. Cabet, A. Terlain, P. Lett, L. Guétaz, J.M. Gentzbittel, Mater. Corros. 57, 147 (2006).
Y. Kurata, Y. Ogawa, H. Nakajima, T. Kondo, in Proc. Workshop Structural Design Criteria for HTR, G. Breitbach, F. Schubert, H. Nickel, Eds. (Fraunhofer IZFP, Saarbrücken, Germany, 1989), p. 275.
P.J. Ennis, K.P. Mohr, H. Schuster, Nucl. Technol. 66, 363 (1984).
P. Kofstad, High Temperature Corrosion (Elsevier, London, 1988).
M.G. Nicholas, C.F. Old, J. Mater Sci. 14, 1 (1979).
L.F. Epstein, Chem. Eng. Prog. Symp. Ser. 20 53, 67 (1957).
J.R. Weeks, C.J. Klamut, D.H. Gurinsky, Proc. Alkali Metal Coolants Symp. (IAEA, Vienna, Austria, 1966), p. 3.
R.C. Asher, D. Davies, S.A. Beetham, Corros. Sci. 17, 545 (1977).
B.A. Shmatko, A.E. Rusanov, Mater. Sci. 36, 689 (2000).
F. Barbier, A. Rusanov, J. Nucl. Mater. 296, 231 (2001).
H. Glasbrenner, J. Konys, G. Mueller, A. Rusanov, J. Nucl. Mater. 296, 237 (2001).
J. Zhang, N. Li, Y. Chen, A.E. Rusanov, J. Nucl. Mater. 336, 1 (2005).
Y. Kurata, M. Futakawa, K. Kikuchi, S. Saito, T. Osugi, J. Nucl. Mater. 301, 28 (2002).
I.G. Wright, P.F. Tortorelli, M. Schütze, “Oxide Growth and Exfoliation on Alloys Exposed to Steam” (EPRI Rep. 1013666, EPRI, Palo Alto, CA, 2007).
C.W. Forsberg, Proc. 2006 Intl. Cong. Adv. Nucl. Power Plants (ICAPP’06) (ANS, La Grange Park, IL, 2006), p. 6292.
D.F. Williams, L.M. Toth, K.T. Clarno “Assessment of Candidate Molten Salt Coolants for the Advanced High-Temperature Reactor (AHTR),” (Rep. ORNL/TM-2006/12, ORNL, Oak Ridge, TN, 2006).
M. Broc, P. Fauvet, J. Sannier, G. Santarini, J. Nucl. Mater. 119, 123 (1983).
J.R. Keiser, D.L. Manning, R.E. Clausing, “Corrosion Resistance of Some Nickel-Base Alloys to Molten Fluoride Salts Containing UF4 and Tellurium,” in Molten Salts (The Electrochemical Society, New York, 1976), pp. 315–328.
J.R. Keiser, “Status of Tellurium–Hastelloy N Studies in Molten Fluoride Salts,” (Rep. ORNL/TM-6002, ORNL, Oak Ridge, TN, 1977).
G.S. Was, P. Ampornrat, G. Gupta, S. Teysseyre, E.A. West, T.R. Allen, K. Sridharan, L. Tan, Y. Chen, X. Ren, C. Pister, J. Nucl. Mater. 371, 176 (2007).
T.R. Allen, L. Tan, Y. Chen, X. Ren, K. Sridharan, G.S. Was, G. Gupta, P. Ampornrat, “Corrosion of Ferritic–Martensitic Alloys in Supercritical Water for GenIV Application,” in Proc. Global 2005 (AESJ, Takasaki City, Japan, 2005), paper 419.
S.S. Hwang, B.H. Lee, J.G. Kim, J. Jang, J. Nucl. Mater. 372, 177 (2008).
Y. Chen, K. Sridharan, S. Ukai, T.R. Allen, J. Nucl. Mater. 371, 118 (2007).
G.J. Yurek, D. Eisen, A. Garratt-Reed, Metall. Trans. A 13, 473 (1982).
A.T. Motta, A. Yilmazbayhan, M.J. Gomes da Silva, R.J. Comstock, G.S. Was, J.T. Busby, E. Gartner, Q. Peng, Y.H. Jeong, J.Y. Park, J. Nucl. Mater. 371, 61 (2007).
S. Teysseyre, Z. Jiao, E. West, G.S. Was, J. Nucl. Mater. 371, 107 (2007).
S. Teysseyre, G.S. Was, “Stress Corrosion Cracking of Neutron Irradiated Steel in Supercritical Water,” in Proc. 13th International Conference on Degradation of Materials in Nuclear Power Systems—Water Reactors, T.R. Allen, J. Busby, P.J. King, Eds. (Canadian Nuclear Society, Toronto, Ontario, Canada, 2007).
E.A. West, S. Teysseyre, Z. Jiao, G.S. Was, “Influence of Irradiation Induced Microstructure on the Stress Corrosion Cracking Behavior of Austenitic Alloys in Supercritical Water,” in Proc. 13th International Conference on Degradation of Materials in Nuclear Power Systems—Water Reactors, T.R. Allen, J. Busby, P.J. King, Eds. (Canadian Nuclear Society, Toronto, Ontario, Canada, 2007).
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Cabet, C., Jang, J., Konys, J. et al. Environmental Degradation of Materials in Advanced Reactors. MRS Bulletin 34, 35–39 (2009). https://doi.org/10.1557/mrs2009.10
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DOI: https://doi.org/10.1557/mrs2009.10