Abstract
The effects of irradiation on chromium performance under different temperatures in Fe-20at%Cr were modeled by modified Marlowe code. Chromium precipitation was observed in FeCr alloy after irradiation; interstitial Chromium atoms are the preferred formation of mixed Fe-Cr dumbbells in the direction of <110> and <111>; interstitial chromium atoms congregated on {111} and {110} plane. The results are compared with experiment observations and are useful to understanding the irradiation performances of FeCr alloy.
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References
Wallenius J. Modeling of chromium precipitation in Fe-Cr alloy. Phys Rev B, 2004, 69(9): 094103–094111
Malerba L, Terentyev D A, Bonny G, et al. Modeling of radiation damage in Fe-Cr alloy. Journal of ASTM International. 2007, 4(6): 1–19
Miller M, Hyde J, Cerezo A, et al. Comparison of low temperature decomposition in Fe-Cr and duplex stainless steels. Applied Surface Science, 1995, 87–88: 323–328
Mathon M H, de Carlan Y, Geoffroy G, et al. A SANS investigation of the irradiation-enhanced α-α’ phases separation in 7–12 Cr martensitic steels. J Nucl Mat, 2003, 312(2,3): 236–248
Pearson W B. A Handbook of Lattice Spacings and Structures of Metals and Alloys. Belfast: Pergamon Press, 1958, 532
Yoshitake T, Yamagata I, Allen T R, et al. Behavior of irradiated type 316 stainless steels under low-strain-rate tensile conditions. Journal of ASTM International, 2005, 2(3): 162–173
Konishi T, Ohsawa K, Abe H, et al. Determination of N-body potential for Fe-Cr alloy system and its application to defect study. Computational Materials Science, 1999, 14(1–4): 108–113
Wallenius J, Abrikosov I A, Chakarova R, et al. Development of an EAM potential for simulation of radiation damage in Fe-Cr alloys. Journal of Nuclear Materials, 2004, 329–333(11):1175–1179
Malerba L, Terentyev D A, Olsson P, et al. Molecular dynamics simulation of displacement cascades in Fe-Cr alloys. Journal of Nuclear Materials. 2004, 329-333(11): 1156–1160
Mendelev M I, Han S, Srolovitz D J, et al. Development of new interatomic potentials appropriate for crystalline and liquid iron. Philosophical Magazine, 2003, 83(35):3977–3994
Ðogo H. Properties of point defects in Fe-Cr alloys. 2006, http://energy-environment.vin.bg.ac.yu/presentations/SixBestPosters/H. DJOGO/Vrnjacka%20Banja.ppt
Chen Jiachao, Yu Gang. Characterization of dislocation loop in bcc ferritic steel by TEM observation and MD simulation. 9th International Conference on Computer Simulation of Radiation Effects in Solids, Beijing, 2008, 42
Gupta G, Was G S. Effect of proton irradiation and grain boundary engineering on stress corrosion cracking of Ferritic-Martensitic alloys in supercritical water. Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors. Salt Lake City, Utah, 2005
Eyre B L, Bullough R. On the formation of interstitial loops in b.c.c. metals. Philos Mag, 1965, 12(1):31–39
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He, X., Yang, W., Qu, Z. et al. Effects of irradiation on chromium’s behavior in ferritic/martensitic FeCr alloy. Front. Energy Power Eng. China 3, 181–183 (2009). https://doi.org/10.1007/s11708-009-0025-x
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DOI: https://doi.org/10.1007/s11708-009-0025-x