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Studies on magnetron-sputtered zirconium-silicide coatings deposited on zirconium alloy for the enhancement of their high-temperature oxidation resistance Cover

Studies on magnetron-sputtered zirconium-silicide coatings deposited on zirconium alloy for the enhancement of their high-temperature oxidation resistance

Open Access
|Nov 2018

References

  1. 1. IAEA. (2017). Nuclear technology review 2017. Vienna: International Atomic Energy Agency. (IAEA/NTR/2017).
  2. 2. Pioro, I. (2016). Handbook on generation IV nuclear reactors. Waltham, MA: Elsevier Ltd.10.1115/1.4035327
  3. 3. Terrani, K. T., Kiggans, J. O., Silva, C. M., Shih, D., Katoh, Y., & Snead, L. L. (2015). Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form. J. Nucl. Mater., 457, 9–17. DOI: 10.1016/j.jnucmat.2014.10.034.10.1016/j.jnucmat.2014.10.034
  4. 4. IAEA. (2014). Accident tolerant fuel concepts. Proceeding of the technical meeting held at the Oak Ridge National Laboratories, USA, 1316 October 2014. Vienna: International Atomic Energy Agency. (IAEA-TECDOC-1797).
  5. 5. Zinkle, S. J., Terrani, K. A., Gehin, J. C., Ott, L. J., & Snead, L. L. (2014). Accident tolerant fuels. A perspective. J. Nucl. Mater., 448, 374–379.10.1016/j.jnucmat.2013.12.005
  6. 6. Morell, P. (2015). Phase 1A Final Report for the AREVA Team Enhanced Accident Tolerant Fuels Concepts. (Report DOE-AFS-0000567). DOI: 10.2172/1172983.10.2172/1172983
  7. 7. Pint, B. A., Terrani, K. A., Yamamoto, Y., & Snead, L. L. (2015). Material selection for accident tolerant fuel cladding. Metall. Mater. Trans. E, 2(3), 190–196. DOI: 10.1007/s40553-015-0056-7.10.1007/s40553-015-0056-7
  8. 8. Kim, H., Yang, J., Kim, W., & Koo, Y. (2016). Development status of accident-tolerant fuel for light water reactors in Korea. Nucl. Eng. Technol., 48, 1–15. https://doi.org/10.1016/j.net.2015.11.011.10.1016/j.net.2015.11.011
  9. 9. Koo, Y., Yang, J., Park, J., Kim, K., Kim, H., Kim, D., Jung, Y., & Song, K. (2014). KAERI’s development of LWR accident-tolerant fuel. Nucl. Technol., 186(2), 295–304. http://dx.doi.org/10.13182/NT13-89.10.13182/NT13-89
  10. 10. Barrett, K., Bragg-Sitton, S., & Galicki, D. (2012). Advanced LWR nuclear fuel cladding system development trade-off study. Idaho National Laboratory. (INL/EXT-12-27090).
  11. 11. Kurata, M. (2016). Research and development methodology for practical use of accident tolerant fuel in light water reactors. Nucl. Eng. Technol., 48, 26–32. DOI: https://doi.org/10.1016/j.net.2015.12.004.10.1016/j.net.2015.12.004
  12. 12. Yueh, K., & Terrani, K. A. (2014). Silicon carbide composite for light water reactor fuel assembly applications. J. Nucl. Mater., 448, 380–388. http://dx.doi.org/10.1016/j.jnucmat.2013.12.004.10.1016/j.jnucmat.2013.12.004
  13. 13. Idarraga-Trujillo, I., Le Flem, M., Brachet, J., Le Saux, M., Hamon, D., Mueller, S., Vanderberghe, V., Tupin, M., Papin, E., Monsierot, E., Billard, A., & Schuster, F. (2013). Assessment at CEA of coated nuclear fuel cladding for LWRs with increased margins in LOCA and beyond LOCA conditions. In Top Fuel 2013 September 15–19, 2013, Charlotte, NC, USA (pp. 860–867).
  14. 14. Rebak, R., Terrani, K., Gassmann, W. P., & Williams, J. B. (2017). Improving nuclear Power plant safety with FeCrAl alloy fuel cladding. MRS Adv., 2(21/22), 1217–1224. https://doi.org/10.1557/adv.2017.5.10.1557/adv.2017.5
  15. 15. Terrani, A. K., Pint, B. A., Kim, Y. J., Unocic, K. A., Silva, C. M., Meyer III, H. M., & Rebak, R. B. (2016). Uniform corrosion of FeCrAl alloys in LWR coolant environments. J. Nucl. Mater., 479, 36–47. http://dx.doi.org/10.1016/j.jnucmat.2016.06.047.10.1016/j.jnucmat.2016.06.047
  16. 16. Yamamoto, Y., Pint, B. A., Terrani, K. A., Field, K. G., Yang, Y., & Snead, L. L. (2015). Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors. J. Nucl. Mater., 467, 703–716. http://dx.doi.org/10.1016/j.jnucmat.2015.10.019.10.1016/j.jnucmat.2015.10.019
  17. 17. Younker, M., & Fratoni, M. (2016) Neutronic evaluation of coating and cladding materials for accident tolerant fuels. Prog. Nucl. Energy, 88, 10–18. http://dx.doi.org/10.1016/j.pnucene.2015.11.006.10.1016/j.pnucene.2015.11.006
  18. 18. Tang, C., Stueber, M., Seifert, H. J., & Steinbruck, M. (2017). Protective coatings on zirconium-based alloys as accident-tolerant fuels (ATF) claddings. Corros. Rev., 35(3), 141–165. DOI: 10.1515/corrrev-2017-0010.10.1515/corrrev-2017-0010
  19. 19. Starosta, W., Barlak, M., Buczkowski, M., Kosińska, A., Sartowska, B., Waliś, L., & Janiak, T. (2015). Analiza mechanizmów tworzenia się oraz właściwości warstw tlenkowych powstających w wyniku rozkładu wody na powierzchni koszulek cyrkonowych oraz zbadanie wpływu modyfikacji struktury warstwy wierzchniej koszulek na procesy generacji wodoru. In J. Michalik, & R. Kocia (Eds.). Analiza procesów generacji wodoru w reaktorze jądrowym w trakcie normalnej eksploatacji i w sytuacjach awaryjnych z propozycjami działań na rzecz podniesienia poziomu bezpieczeństwa jądrowego (pp. 55–72). Warszawa: Institute of Nuclear Chemistry and Technology.
  20. 20. Mariani, R., Medvedev, P., Porter, D. L., Hayes, S. L., Cole, J. I., & Bai, X. (2013). Novel accident-tolerant fuel meat and cladding. In Top Fuels, September 15–19, 2013, Charlotte, NC, USA (pp. 763–770).
  21. 21. Yeom, H., Maier, B., Mariani, R., Bai, D., Fronek, S., Xu, P., & Sridharan, K. (2017). Magnetron sputter deposition of zirconium-silicide coating for mitigating high temperature oxidation of zirconium-alloy. Surf. Coat. Technol., 316, 30–38. http://dx.doi.org/10.1016/j.surfcoat.2017.03.018.10.1016/j.surfcoat.2017.03.018
  22. 22. Kaiser, A., Lobert, M., & Telle, R. (2008). Thermal stability of zircon (ZrSiO4). J. Eur. Ceram. Soc., 28, 2199–2211. DOI: 10.1016/j.jeurceramsoc.2007.12.040.10.1016/j.jeurceramsoc.2007.12.040
  23. 23. Lavrenko, V. A., Shemet, V. Zh., & Goncharuk, A. V. (1985). Studies on mechanism of high-temperature oxidation of molybdenium, tungsten and zirconium disilicides by differential thermal analysis. Thermochim. Acta, 93, 501–504. https://doi.org/10.1016/0040-6031(85)85126-1.10.1016/0040-6031(85)85126-1
  24. 24. Ueno, S., Ogji, T., & Lin, H. T. (2007). Corrosion and recession behavior of zircon in water vapor environment at high temperature. Corros. Sci., 49(3), 1162–1171. https://doi.org/10.1016/j.corsci.2006.08.013.10.1016/j.corsci.2006.08.013
DOI: https://doi.org/10.2478/nuka-2018-0009 | Journal eISSN: 1508-5791 | Journal ISSN: 0029-5922
Language: English
Page range: 73 - 79
Submitted on: Nov 25, 2017
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Accepted on: Sep 18, 2018
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Published on: Nov 2, 2018
In partnership with: Paradigm Publishing Services
Publication frequency: 4 issues per year

© 2018 Wojciech Starosta, Viera K. Semina, Jerzy Smolik, Lech Waliś, Michał Rydzewski, Bożena Sartowska, published by Institute of Nuclear Chemistry and Technology
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.