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NTIS 바로가기Advances in materials science, v.19 no.2, 2019년, pp.54 - 71
Trybuś, B. (Gdansk University of Technology, Faculty of Mechanical Engineering, Department of Materials Science and Welding Engineering, Narutowicza 11) , Olive, J. M. (sk, Poland) , Lenoir, N. (C.N.R.S., I2M, UMR 5295, 351 cours de la Liberation, Talence33405, France) , Zieliński, A. (PLACAMAT : Plateforme Aquitaine de Caracté)
ABSTRACTThe investigations of high-temperature oxidation of zirconium alloys, applied for fuel pellets in nuclear power plants, are usually limited to oxidation kinetics, phase transformations and microstructural characterization. The purpose of this research was to characterize the degradation phenomena occurring within oxide layer and at the interface oxide/metal, on internal and external Zircaloy-2 tube surfaces, below and over crystalline transformation temperature of zirconium oxides. The commercial tubes were oxidized at 1273 K and 1373 K in calm air for 30 min and then examined with a technique novel for such purpose, namely a high-resolution X-ray computer tomography. The light microscopy was used to examine the cross-surfaces. The obtained results show that the form and intensity of oxide damage is significant and it is in a complicated way related to oxidation temperature and on whether external or internal tube surface is studied. The found oxide layer damage forms include surface cracks, the detachment of oxide layers, the appearance of voids, and nodular corrosion. The oxidation effects and damage appearance are discussed taking into account the processes such as formation of oxides, their phase transformation, stress-enhanced formation and propagation of cracks, diffusion of vacancies, formation of nitrides, diffusion of hydrogen into interface oxide-metal, incubation of cracks on second phase precipitates are taken into account to explain the observed phenomena.
10.1016/j.jnucmat.2012.06.026 1. Proff C., Abolhassani S., Lemaignan C., Oxidation behaviour of zirconium alloys and their precipitates - A mechanistic study. J. Nucl. Mater. 432 (2013) 222-238.10.1016/j.jnucmat.2012.06.026
10.1016/j.jnucmat.2011.09.014 3. Park K., Yang S., Ho K., The effect of high pressure steam on the oxidation of low-Sn Zircaloy-4 at temperatures between 700 and 900 °C. J. Nucl. Mater. 420 (2012) 39-48.10.1016/j.jnucmat.2011.09.014
10.1016/j.jnucmat.2011.04.012 4. Steinbrück M., Böttcher M., Air oxidation of Zircaloy-4, M5 and ZIRLO cladding alloys at high temperatures. J. Nucl. Mater. 414 (2011) 276-285.10.1016/j.jnucmat.2011.04.012
10.1016/j.jnucmat.2010.07.038 5. Coindreau C., Duriez C., Ederli S. : Air oxidation of Zircaloy-4 in the 600-1000 °C temperature range: Modeling for ASTEC code application. J. Nucl. Mater. 405 (2010) 207-215.10.1016/j.jnucmat.2010.07.038
10.4236/ampc.2013.32023 6. Selmi N., Sari A., Study of oxidation kinetics in air of Zircaloy-4 by in situ X-Ray diffraction. Adv. Mater. Phys. Chem. 3 (2013) 168-173.10.4236/ampc.2013.32023
10.1016/j.jnucmat.2011.05.028 7. Sawabe T., Sonoda T., Furuya M., Kitajima S., Kinoshita M., Tokiwai M., Microstructure of oxide layers formed on zirconium alloy by air oxidation, uniform corrosion and fresh-green surface modification. J. Nucl. Mater. 419 (2011) 310-319.10.1016/j.jnucmat.2011.05.028
10.1016/j.corsci.2013.05.007 8. Gong W, Zhang H, Qiao Y., Tian H., Ni X., Li Z., Wang X., Grain morphology and crystal structure of pre-transition oxides formed on Zircaloy-4. Corr. Sci. 74 (2013) 323-331.10.1016/j.corsci.2013.05.007
10.1016/j.jnucmat.2016.03.009 9. Harlow W., Ghassemi H., Taheri M.L., Determination of the initial oxidation behavior of Zircaloy-4 by in-situ TEM. J. Nucl. Mater. 474 (2016) 126-133.10.1016/j.jnucmat.2016.03.009
10.1179/mht.2000.005 10. Ishii Y., Sykes J.M., Microstructure of oxide layers formed on Zircaloy-2 in air at 450°C. Mater. High Temp. 17 (2014) 23-28.10.1179/mht.2000.005
10.1016/j.jnucmat.2012.05.003 11. Gosset D., Le Saux M.L., Simeone D., Gilbon D. : New insights in structural characterization of zirconium alloys oxidation at high temperature. J. Nucl. Mater. 429 (2012) 19-24.10.1016/j.jnucmat.2012.05.003
10.1016/j.jnucmat.2014.12.067 12. Gosset D., Le Saux M.L., In-situ X-ray diffraction analysis of zirconia layer formed on zirconium alloys oxidized at high temperature. J. Nucl. Mater. 458 (2015) 245-252.10.1016/j.jnucmat.2014.12.067
10.1016/j.jnucmat.2007.02.011 13. Baek J.H., Jeong Y.H., Breakaway phenomenon of Zr-based alloys during a high-temperature oxidation. J. Nucl. Mater. 372 (2008) 152-159.10.1016/j.jnucmat.2007.02.011
10.1016/j.jnucmat.2013.10.044 14. Yamato M, Nagase F, Amaya M., Reduction in the onset time of breakaway oxidation on Zircaloy cladding ruptured under simulated LOCA conditions. J. Nucl. Mater. 445 (2014) 78-83.10.1016/j.jnucmat.2013.10.044
10.1007/s11085-017-9737-1 15. Fettré D., Favergeon J., Bouvier S., Detection of breakaway for a high-temperature oxidation of pure zirconium using acoustic emission correlated to thermogravimetry. Oxid. Met. 87 (2017) 367-379.10.1007/s11085-017-9737-1
10.1016/j.jnucmat.2011.06.039 16. Kim H.G., Kim I.H., Choi B.K., Park Y.Y., A study of the breakaway oxidation behavior of zirconium cladding materials. J. Nucl. Mater. 418 (2011) 186-197.10.1016/j.jnucmat.2011.06.039
10.1016/S1005-0302(10)60132-6 17. Kim H.H., Kim J.H., Moon J.Y., Lee H.S., Kim J.J., Chai Y.S., High-temperature oxidation behavior of Zircaloy-4 and Zirlo in steam ambient. J. Mater. Sci. Technol. 26 (2010) 827-832.10.1016/S1005-0302(10)60132-6
10.1515/adms-2017-0030 18. Zienkiewicz N., Paradowska J., Serbinski W., Gajowiec G., Hernik A., Zielinski A., Oxidation and hydrogen behavior in Zr-2Mn alloy. Adv. Mater. Sci. 18 (2018) 37-48.10.1515/adms-2017-0030
10.1016/j.corsci.2017.09.014 19. Annand K., Nord M., Maclaren I., Gass M., The corrosion of Zr(Fe, Cr)2 and Zr2Fe secondary phase particles in Zircaloy-4 under 350 °C pressurised water conditions. Corr. Sci. 128 (2017) 213-223.10.1016/j.corsci.2017.09.014
10.1016/j.jnucmat.2011.03.010 20. Park D.J., Park J.Y., Jeong J.H., Microstructural analysis and XPS investigation of nodular oxides formed on Zircaloy-4. J. Nucl. Mater. 412 (2011) 233-238.10.1016/j.jnucmat.2011.03.010
10.1016/j.jnucmat.2017.10.013 21. Lee C.M., Mok Y.K., Sohn D.S. : High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding. J. Nucl. Mater. 496 (2017) 343-352.10.1016/j.jnucmat.2017.10.013
10.1016/j.jnucmat.2014.05.006 22. Nikulin S.A., Rogachev S.O., Rozhnov A.B., Gusev A.Yu., Malgin A.G., Abramov N.N., Zharotsheva K.S., Khatkevich V.M., Koteneva M.V., Li E.V., The mechanism and kinetics of the fuel cladding failure during loading after high-temperature oxidation. J. Nucl. Mater. 452 (2014) 102-109.10.1016/j.jnucmat.2014.05.006
10.1016/j.corsci.2011.08.013 23. Ni N., Lozano-Perez S., Sykes J.M., Smith G.D.W., Grovenor C.R.M., Focussed ion beam sectioning for the 3D characterisation of cracking in oxide scales formed on commercial ZIRLO™ alloys during corrosion in high temperature pressurised water. Corr. Sci. 53 (2011) 4073-4083.10.1016/j.corsci.2011.08.013
10.3184/096034012X13334555476487 24. Ni N., Lozano-Perez S., Sykes J., Grovenor C. : Multi-scale characterisation of oxide on zirconium alloys. Mater. High. Temp. 29 (2014) 166-170.10.3184/096034012X13334555476487
10.1007/s11085-011-9249-3 25. Steinbrück M., Vér N., Große M., Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600-1200 °C. Oxid. Met. 76 (2011) 215-232.10.1007/s11085-011-9249-3
10.1007/s11085-005-6563-7 26. Favergeon J., Montesin T., Mechano-Chemical Aspects of High Temperature Oxidation: A Mesoscopic Model Applied to Zirconium Alloys. Met. Oxid. 64 (2005) 252-279.10.1007/s11085-005-6563-7
10.1016/j.jnucmat.2008.07.002 27. Duriez C., Dupont T., Schmet B., Enoch F., Zircaloy-4 and M5® high temperature oxidation and nitriding in air. J. Nucl. Mater. 380 (2008) 30-45.10.1016/j.jnucmat.2008.07.002
10.1016/j.ijhydene.2016.01.174 28. Zeng C., Ling Y., Bai Y., Zhang R., Dai X., Chen Y., Hydrogen permeation characteristic of nanoscale passive films formed on different zirconium alloys. Intl. J. Hydrogen Energy 41 (2016) 7676-7690.10.1016/j.ijhydene.2016.01.174
10.1515/htmp-2017-0074 29. Zieliński A., Cymann A., Gumiński A., Hernik A., Gajowiec G., Influence of high temperature oxidation hydrogen absorption and degradation of Zircaloy-2 and Zr 700 alloys. High Temp. Mater. Proc. 38 (2019) 8-15.10.1515/htmp-2017-0074
10.1016/S0022-3115(01)00695-X 30. Yoo H.-I., Koo B.-J., Hong J.-O., Hwang I.-S., Yeong I.-H., A working hypothesis on oxidation kinetics of Zircaloy. J. Nucl. Mater. 299 (2001) 235-241.10.1016/S0022-3115(01)00695-X
10.1016/S0925-8388(02)00527-3 31. Lee K. W., Hong S.I., Zirconium hydrides and their effect on the circumferential mechanical properties of Zr-Sn-Fe-Nb tubes. J. Alloys Cmpds 346 (2002) 302-307.10.1016/S0925-8388(02)00527-3
32. Kurpaska L., Jozwik I., Jagielski J., Study of sub-oxide phases at the metal-oxide interface in oxidized pure zirconium and Zr-1.0% Nb alloy by using SEM/FIB/EBSD and EDS techniques. J. Nucl. Mater. 299 (2001) 235-241.
10.1016/j.jnucmat.2014.09.073 33. De Gabory B., Motta A.T., Wang K., Transmission electron microscopy characterization of Zircaloy-4 and ZIRLO™ oxide layers. J. Nucl. Mater. 456 (2015) 272-280.10.1016/j.jnucmat.2014.09.073
10.1016/j.jnucmat.2012.06.039 34. Tejland P., Andrén H.-A., Origin and effect of lateral cracks in oxide scales formed on zirconium alloys. J. Nucl. Mater. 430 (2012) 64-71.10.1016/j.jnucmat.2012.06.039
10.1016/j.corsci.2015.03.004 35. Guerain M., Duriez C., Grosseau-Poussard J.L., Mermoux M., Review of stress fields in zirconium alloys corrosion scales. Corr. Sci. 95 (2015) 11-21.10.1016/j.corsci.2015.03.004
10.1080/09603409.2017.1392412 36. Baris S., Abolhassani Y.L., Chiu L., Evans H.E., (2018) Observation of crack microstructure in oxides and its correlation to oxidation and hydrogen-uptake by 3D FIB Tomography - case of Zr-ZrO2 in reactor. Mater. High Temp. 35 (2018) 14-21.10.1080/09603409.2017.1392412
10.1016/j.anucene.2011.10.019 37. Birchley J., Fernandez-Moguel L. : Simulation of air oxidation during a reactor accident sequence: Part 1 - Phenomenology and model development. Ann. Nucl. Energy. 40 (2012) 163-170.10.1016/j.anucene.2011.10.019
10.1016/S0022-3115(98)00613-8 38. Rudling P., Wikmark G.A., A unified model of Zircaloy BWR corrosion and hydriding mechanisms. J. Nucl. Mater. 265 (1999) 44-59.10.1016/S0022-3115(98)00613-8
10.1016/j.jnucmat.2005.10.012 39. Yilmazbayhan A., Breval E., Motta A.T., Comstock R.J., Transmission electron microscopy examination of oxide layers formed on Zr alloys. J. Nucl. Mater. 349 (2006) 265-281.10.1016/j.jnucmat.2005.10.012
10.1016/j.pnucene.2009.07.012 40. Steinbrück M., Birchley J., Boldyrev A.V., Goryachev A.V., Grosse M., Haste T.J., Hózer Z., Kisselev A.E., Nalivaev V.I., Semishkin V.P., Sepold L., Stuckert J., Vér N., Veshchunov M.S., High temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys. Progr. Nucl. Energy 52 (2010) 19-36.10.1016/j.pnucene.2009.07.012
10.1016/0022-3115(83)90199-X 41. Kawashima N.K.S.H., Mechanism of zircaloy nodular corrosion J. Nucl. Mater. 119 (1983) 229-239.10.1016/0022-3115(83)90199-X
10.1016/j.jnucmat.2009.04.003 42. Likhanskii V.V., Evdokimov L.A., Effect of additives on the susceptibility of zirconium alloys to nodular corrosion. J. Nucl. Mater. 392 (2009) 447-452.10.1016/j.jnucmat.2009.04.003
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