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Effects of alloying elements on the formation of <c>-component loops in Zr alloy Excel under heavy ion irradiation

Published online by Cambridge University Press:  14 April 2015

Yasir Idrees ,
Elisabeth M. Francis ,
Zhongwen Yao ,
Andreas Korinek ,
Marquis A. Kirk ,
Mohammad Sattari ,
Michael Preuss  and
Mark R. Daymond
Yasir Idrees*
Affiliation:
Department of Mechanical and Materials Engineering, Queen's University, Kingston, Ontario K7L 3N6, Canada
Elisabeth M. Francis
Affiliation:
The University of Manchester, Manchester Materials Science Centre, Manchester M13 9PL, United Kingdom
Zhongwen Yao
Affiliation:
Department of Mechanical and Materials Engineering, Queen's University, Kingston, Ontario K7L 3N6, Canada
Andreas Korinek
Affiliation:
Department of Materials Science and Engineering, and Canadian Center for Electron Microscopy, McMaster University, Hamilton, Ontario L8S 4M1, Canada
Marquis A. Kirk
Affiliation:
Material Science Division, Argonne National Laboratory, Argonne, Illinois 60439, USA
Mohammad Sattari
Affiliation:
Department of Mechanical and Materials Engineering, Queen's University, Kingston, Ontario K7L 3N6, Canada
Michael Preuss
Affiliation:
The University of Manchester, Manchester Materials Science Centre, Manchester M13 9PL, United Kingdom
Mark R. Daymond
Affiliation:
Department of Mechanical and Materials Engineering, Queen's University, Kingston, Ontario K7L 3N6, Canada
*
a)Address all correspondence to this author. e-mail: 9yi@queensu.ca
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Abstract

We report here the microstructural changes occurring in the zirconium alloy Excel (Zr–3.5 wt% Sn–0.8Nb–0.8Mo–0.2Fe) during heavy ion irradiation. In situ irradiation experiments were conducted at reactor operating temperatures on two Zr Excel alloy microstructures with different states of alloying elements, with the states achieved by different solution heat treatments. In the first case, the alloying elements were mostly concentrated in the beta (β) phase, whereas, in the second case, large Zr3(Mo,Nb,Fe)4 secondary phase precipitates (SPPs) were grown in the alpha (α) phase by long term aging. The heavy ion induced damage and resultant compositional changes were examined using transmission electron microscopy (TEM) in combination with scanning transmission electron microscope (STEM)-energy dispersive x-ray spectroscopy (EDS) mapping. Significant differences were seen in microstructural evolution between the two different microstructures that were irradiated under similar conditions. Nucleation and growth of <c>-component loops and their dependence on the alloying elements are a major focus of the current investigation. It was observed that the <c>-component loops nucleate readily at 100, 300, and 400 °C after a threshold incubation dose (TID), which varies with irradiation temperature and the state of alloying elements. It was found that the TID for the formation of <c>-component loops increases with decrease in irradiation temperature. Alloying elements that are present in the form of SPPs increase the TID compared to when they are in the β phase solid solution. Dose and temperature dependence of loop size and density are presented. Radiation induced redistribution and clustering of alloying elements (Sn, Mo, and Fe) have been observed and related to the formation of <c>-component loops. It has been shown that at the higher temperature tests, irradiation induced dissolution of precipitates occurs whereas irradiation induced amorphization occurs at 100 °C. Furthermore, dose and temperature seem to be the main factors governing the dissolution of SPPs and redistribution of alloying elements, which in turn controls the nucleation and growth of <c>-component loops. The correlation between the microstructural evolution and microchemistry has been found by EDS and is discussed in detail.

Keywords

Zr alloy Excelirradiation growthion irradiation-component loopspressure tube
Type
Articles
Information
Journal of Materials Research , Volume 30 , Issue 9: Focus Issue: Characterization and Modeling of Radiation Damage on Materials: State of the Art, Challenges, and Protocols , 14 May 2015 , pp. 1310 - 1334
Copyright
Copyright © Materials Research Society 2015 

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Footnotes

Contributing Editor: Djamel Kaoumi

References

REFERENCES

Peng, D.Q., Bai, X.D., Chen, X.W., Zhou, Q.G., Liu, X.Y., and Yu, R.H.: Effect of self ion bombardment on the corrosion behavior of zirconium. Nucl. Instrum. Methods Phys. Res., Sect. B 215, 394 (2004).CrossRefGoogle Scholar
Idrees, Y., Yao, Z., Kirk, M.A., and Daymond, M.R.: In situ study of defect accumulation in zirconium under heavy ion irradiation. J. Nucl. Mater. 433, 95 (2013).CrossRefGoogle Scholar
Azevedo, C.R.F.: A review on neutron-irradiation-induced hardening of metallic components. Eng. Failure Anal. 18, 1921 (2011).CrossRefGoogle Scholar
Chow, C.K. and Khartabil, H.F.: Conceptual fuel channel designs for CANDU-SCWR. Nucl. Eng. Technol. 40(2), 139 (2008).Google Scholar
Ibrahim, E.F., Price, E.G., and Wysiekiersky, A.G.: Creep and stress-rupture of high strength zirconium alloys. Can. Metall. Q. 11(1), 273 (1972).CrossRefGoogle Scholar
Causey, A.R., Carpenter, G.J.C., and MacEwen, S.R.: In-reactor stress relaxation of selected metals and alloys at low temperatures. J. Nucl. Mater. 90, 216 (1980).Google Scholar
Cheadle, B.A., Holt, R.A., Fidleris, V., Causey, A.R., and Urbanic, V.F.: High-strength, creep-resistant excel pressure tubes. In Zirconium in the Nuclear Industry: Fifth International Symposium, ASTM, STP.754, Franklin, D.G. ed.; American Society for Testing and Materials, Philidelphia, PA, 1982; p. 193.Google Scholar
Griffiths, M.: A review of microstructure evolution in zirconium alloys during irradiation. J. Nucl. Mater. 159, 190 (1988).Google Scholar
Chow, C.K., Khartabil, H.F., and Bushby, S.J.: A fuel channel design for CANDU-SCWR. Presented at The 14th International Conference on Nuclear Engineering, Paper No. ICONE14-89679, 2006; p. 677.Google Scholar
Salinas-Rodriguez, A., Akben, M.G., Jonas, J.J., and Ibrahim, E.F.: Comparative study of the deformation behaviour of Zr-2.5 wt% Nb and excel pressure tube alloys. Can. Metall. Q. 24(3), 259 (1985).CrossRefGoogle Scholar
Holt, R.A. and Gilbert, R.W.: <c> Component dislocations in annealed Zircaloy irradiated at about 570 K. J. Nucl. Mater. 137, 185 (1986).Google Scholar
Fidleris, V., Tucker, R., and Adamson, R.B.: An overview of microstructural and experimental factors that affect the irradiation growth behavior of zirconium alloys. In Zirconium in the Nuclear Industry: 7th International Symposium, ASTM STP 939, Adamson, R.B. and Van Swam, L.F.P. eds.; American Society for Testing and Materials, Philadelphia PA, 1987; p. 49.Google Scholar
Rogerson, A. and Murgatroyd, R.A.: “Breakaway” growth in annealed Zircaloy-2 at 353 K and 553 K. J. Nucl. Mater. 113(2–3), 256 (1983).Google Scholar
Jostsons, A., Kelly, P.M., Blake, R.G., and Farrel, K.: Neutron irradiation-induced defect structures in zirconium. In Effects of Radiations in Structural Materials, ASTM STP.683, Sprague, J.A. and Kramer, D. eds.; American Society for Testing and Materials, Philidelphia, PA, 1979; p. 46.Google Scholar
Griffiths, M. and Gilbert, R.W.: The formation of c-component defects in zirconium alloys during neutron irradiation. J. Nucl. Mater. 150(2), 169 (1987).Google Scholar
Northwood, D.O., Gilbert, R.W., Bahen, L.E., Kelly, P.M., Blake, R.G., Jostsons, A., Madden, P.K., Faulkner, D., Bell, W., and Adamson, R.B.: Characterization of neutron irradiation damage in zirconium alloys-an international “round-robin” experiment. J. Nucl. Mater. 79(2), 379 (1979).CrossRefGoogle Scholar
Jostsons, A., Blake, R.G., Napier, J.G., Kelly, P.M., and Farrell, K.: Faulted loops in neutron-irradiated zirconium. J. Nucl. Mater. 68(3), 267 (1977).CrossRefGoogle Scholar
Holt, R.A. and Gilbert, R.W.: c-Component dislocations in neutron irradiated Zircaloy-2. J. Nucl. Mater. 116(1), 127 (1983).Google Scholar
Herring, R.A. and Loretto, M.H.: Solute interaction with Point Defects in HEVM Irradiated Zirconium Alloys. Proceedings of the 6th Annual Conference Of the Canadian Nuclear Society, French, P.M. and Phillips, G.J. eds.; Ottawa, 1985.Google Scholar
Yang, W.J.S.: Some observations of the role of irradiation-induced microstructures in irradiation growth “Breakaway” in Zircaloy-4. International Conference On Fundamental Mechanisms of Radiation-Induced Creep and Growth, Hecla Island, Manitoba, Canada, 1987.Google Scholar
De Carlan, Y., Régnard, C., Griffiths, M., and Gilbon, D.: Influence of iron in the nucleation of <c> component dislocation loops in irradiated Zircaloy-4. In Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP.1295, Bradley, E.R. and Sabol, G.P. eds.; American Society for Testing and Materials, Philidelphia, PA, 1996; p. 638.CrossRefGoogle Scholar
Lee, J.H., Hwang, S.K., Yasuda, K., and Kinoshita, C.: Effect of molybdenum on electron radiation damage of Zr-base alloys. J. Nucl. Mater. 289(3), 334 (2001).CrossRefGoogle Scholar
Idrees, Y., Yao, Z., Sattari, M., Kirk, M.A., and Daymond, M.R.: Irradiation induced microstructural changes in Zr-excel alloy. J. Nucl. Mater. 441(1–3), 138 (2013).CrossRefGoogle Scholar
Hengstler-Eger, R.M., Baldo, P., Beck, L., Dorner, J., Ertl, K., Hoffmann, P.B., Hugenschmidt, C., Kirk, M.A., Petry, W., Pikart, P., and Rempel, A.: Heavy ion irradiation induced dislocation loops in AREVA’s M5® alloy. J. Nucl. Mater. 423(1–3), 170 (2012).CrossRefGoogle Scholar
Griffiths, M.: Microstructure evolution in Zr alloys during Irradiation: Dose, dose rate, and impurity dependence. In Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505, Bruce, K. and Magnus, L. eds.; American Society for Testing and Materials, Philidelphia, PA, 2009; p. 19.Google Scholar
Carpenter, G.J.C. and Watters, J.F.: A study of electron irradiation damage in zirconium using a high voltage electron microscope. J. Nucl. Mater. 96(3), 213 (1981).CrossRefGoogle Scholar
Tucker, R., Fidleris, V., and Adamson, R.B.: High-fluence irradiation growth of zirconium alloys at 644 to 725 K. In Zirconium in the Nuclear Industry: Sixth International Symposium, ASTM STP.824, Franklin, D.G. and Adamson, R.B. eds.; American Society for Testing and Materials, Philidelphia, PA, 1984; p. 472.Google Scholar
Murgatroyd, R.A. and Rogerson, A.: An assessment of the influence of microstructure and test conditions on the irradiation growth phenomenon in zirconium alloys. J. Nucl. Mater. 90(1–3), 240 (1980).CrossRefGoogle Scholar
Rogerson, A.: Irradiation growth in zirconium and its alloys. J. Nucl. Mater. 159, 43 (1988).CrossRefGoogle Scholar
Hood, G.M.: Point defect diffusion in α-Zr. J. Nucl. Mater. 159, 149 (1988).Google Scholar
Sattari, M., Holt, R.A., and Daymond, M.R.: Aging response and characterization of precipitates in Zr alloy Excel pressure tube material. J. Nucl. Mater. 452, 265 (2014).Google Scholar
Sattari, M., Holt, R.A., and Daymond, M.R.: Phase transformation temperatures of Zr alloy Excel. J. Nucl. Mater. 435(1–3), 241 (2013).Google Scholar
Ziegler, F., Biersack, J., and Littmark, U.: The Stopping and Range of Ions in Matter (Pergamon Press, Oxford, UK, 1985).Google Scholar
Was, G.S.: Fundamentals of Radiation Materials Science: Metals and Alloys (Springer, New York, NY, 2007).Google Scholar
Stoller, R.E., Toloczko, M.B., Was, G.S., Certain, A.G., Dwaraknath, S., and Garner, F.A.: On the use of SRIM for computing radiation damage exposure. Nucl. Instrum. Methods Phys. Res., Sect. B 310, 75 (2013).CrossRefGoogle Scholar
Li, M., Kirk, M.A., Baldo, P.M., Xu, D., and Wirth, B.D.: Study of defect evolution by TEM with in situ ion irradiation and coordinated modeling. Philos. Mag. 92(16), 2048 (2012).Google Scholar
Banerjee, S. and Krishnan, R.: Martensitic transformation in zirconium-niobium alloys. Acta Metall. 19(12), 1317 (1971).CrossRefGoogle Scholar
Srivastava, D., Mukhopadhyay, P., Banerjee, S., and Ranganathan, S.: Morphology and substructure of lath martensites in dilute Zr-Nb alloys. Mater. Sci. Eng., A 288(1), 101 (2000).Google Scholar
Banerjee, S. and Krishnan, R.: Martensitic transformation in Zr-Ti alloys. Metall. Trans. 4(8), 1811 (1973).Google Scholar
Sato, K., Matsumoto, H., Kodaira, K., Konno, T.J., and Chiba, A.: Phase transformation and age-hardening of hexagonal α′ martensite in Ti-12 mass%V-2 mass%Al alloys studied by transmission electron microscopy. J. Alloys. Compd. 506(2), 607 (2010).Google Scholar
Mantani, Y., Takemoto, Y., Hida, M., Sakakibara, A., and Tajima, M.: Phase transformation of α″ martensite structure by aging in Ti-8 mass%Mo Alloy. Mater. Trans. 45(5), 1629 (2004).Google Scholar
Griffiths, M., Loretto, M.H., and Smallman, R.E.: Electron damage in zirconium: II. Nucleation and growth of c-component loops. J. Nucl. Mater. 115(2), 323 (1983).Google Scholar
Gilbon, D. and Simonot, C.: Effect of irradiation on the microstructure of zircaloy-4. In Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP.1245, Garde, E.M. and Bradley, E.R. eds.; American Society for Testing and Materials: West Conshohocken, PA, 1994; p. 521.Google Scholar
Griffiths, M., Gilbert, R.W., and Fidleris, V.: Accelerated irradiation growth of zirconium alloys. In Zirconium in the NuclearIndustry: Eighth International Symposium, ASTM STP.1023, Van Swam, L.F.P. and Eucken, C.M. eds.; American Society for Testing and Materials: Philadelphia, PA, 1989; p. 658.Google Scholar
Nelson, R.S., Hudson, J.A., and Mazey, D.J.: The stability of precipitates in an irradiation environment. J. Nucl. Mater. 44, 318 (1972).CrossRefGoogle Scholar
Griffiths, M.: Comments on precipitate stability in neutron-irradiated Zircaloy-4. J. Nucl. Mater. 170(3), 294 (1990).Google Scholar
Holt, R.A., Causey, A.R., Christodoulou, N., Griffiths, M., Ho, E.T.C., and Woo, C.H.: Non-linear irradiation growth of cold-worked Zircaloy-2. In Zirconium in Nuclear Industry: Eleventh International Symposium, ASTM STP.1295, Bradly, E.R. and Sabol, G.P. eds.; American Society for Testing and Materials, Philidelphia, PA, 1996; p. 623.Google Scholar
Griffiths, M., Gilbon, D., Regnard, C., and Lemaignan, C.: HVEM study of the effects of alloying elements and impurities on radiation damage in Zr-alloys. J. Nucl. Mater. 205, 273 (1993).Google Scholar
Griffiths, M., Holt, R.A., and Rogerson, A.: Microstructural aspects of accelerated deformation of Zircaloy nuclear reactor components during service. J. Nucl. Mater. 225, 245 (1995).Google Scholar
Buckley, S.N. and Manthorpe, S.A.: Dislocation loop nucleation and growth in zirconium-2.5 wt% niobium alloy during 1 MeV electron irradiation. J. Nucl. Mater. 90(1), 169 (1980).Google Scholar
Dubinko, V.I. and Klepikov, V.F.: The influence of non-equilibrium fluctuations on radiation damage and recovery of metals under irradiation. J. Nucl. Mater. 362(2), 146 (2007).Google Scholar
Williams, C.D., Ells, C.E., and Dixon, P.R.: Development of high strength zirconium alloys. Can. Metall. Q. 11(1), 257 (1972).CrossRefGoogle Scholar
Carpenter, G.J.C. and Walters, J.F.: Irradaition damage recovery in some zirconium alloys. In Zirconium in Nuclear Applications, ASTM STP 551, American Society for Testing and Materials, Philidelphia, PA, 1974; p. 400.Google Scholar
Abriata, J.P., Bolcich, J.C., and Arias, D.: The Sn-Zr (Tin-Zirconium) system. Bull. Alloy Phase Diagrams 4, 147 (1983).CrossRefGoogle Scholar
Toffolon, C., Brachet, J.C., Servant, C., Legras, L., Charquet, D., Barberis, P., and Mardon, J.P.: Contribution of thermodynamic calculations to metallurgical studies of multi-component zirconium based alloys. In ASTM STP, 1423, ASTM, Philidelphia, PA, 2002; p. 361.Google Scholar
Hood, G.M. and Schultz, R.J.: Tracer diffusion in α-Zr. Acta. Metall. 22(4), 459 (1974).Google Scholar
Woo, O.T. and Carpenter, G.J.C.: Radiation-induced precipitation in Zircaloy-2. J. Nucl. Mater. 159, 397 (1988).Google Scholar
Zinkevich, M. and Mattern, N.: Thermodynamic assessment of the Mo-Zr system. J. Phase Equilib. 23(2), 156 (2002).Google Scholar
Russell, K.C.: Phase stability under irradiation. Prog. Mater. Sci. 28, 229 (1984).Google Scholar
Doriot, S., Gilbon, D., Bechade, J-L., Mathon, M-H., Legras, L., and Mardon, J-P.: Microstructural stability of M5™ Alloy irradiated up to high neutron fluences. J. ASTM Int. 2(7), 175 (2005).Google Scholar
Griffiths, M., Gilbert, R.W., and Carpenter, G.J.C.: Phase instability, decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and -4 during neutron irradiation. J. Nucl. Mater. 150(1) 53 (1987).Google Scholar
Nuttall, K. and Faulkner, D.: The effect of irradiation on the stability of precipitates in Zr-2.5 wt.% Nb alloys. J. Nucl. Mater. 67(1–2), 131 (1977).Google Scholar
Kruger, R.M. and Adamson, R.B.: Precipitate behavior in zirconium-based alloys in BWRs. J. Nucl. Mater. 205, 242 (1993).Google Scholar
Onimus, F. and Béchade, J.L.: Radiation effects in zirconium alloys. In Comprehensive Nuclear Materials, Vol. 4, Konings, R.J.M., ed. Elsevier, Amsterdam, Netherlands, 2012; p. 31.Google Scholar
Motta, A.T.: Amorphization of intermetallic compounds under irradiation-A review. J. Nucl. Mater. 244, 227 (1997).Google Scholar
Motta, A.T. and Olander, D.R.: Theory of electron-irradiation-induced amorphization. Acta Metall. Mater. 38(11), 2175 (1990).CrossRefGoogle Scholar
Yang, W.J.S.: Precipitate stability in neutron-irradiated Zircaloy-4. J. Nucl. Mater. 158, 71 (1988).Google Scholar
Etoh, Y. and Shimada, S.: Neutron irradiation effects on intermetallic precipitates in Zircaloy as a function of fluence. J. Nucl. Mater. 200(1), 59 (1993).Google Scholar