Interaction of metallic zirconium and its alloys Zry-2 and E110 with molten eutectic salt of LiF–NaF–KF containing zirconium fluoride components

References

Aomi, M., Baba, T., Miyashita, T., Kamimura, K., Yasuda, T., Shinohara, Y., & Takeda, T. (2008). Evaluation of hydride reorientation behavior and mechanical properties for high-burnup fuel-cladding tubes in interim dry storage. Journal of American Society for Testing of Materials International, 5, 651–671.10.1520/STP48161SSearch in Google Scholar

ASTM International (1999). ASTM standard: Standard practice for preparing, cleaning, and evaluating corrosion test specimens. ASTM G1 – 03(2011). Philadelphia, PA, USA.Search in Google Scholar

Barborík, P., Vasková, Z., Boča, M., & Priščák, J. (2014). Physicochemical properties of the system (LiF + NaF + KF(eut.) + Na₇Zr₆F₃₁): Phase equilibria, density and volume properties, viscosity and surface tension. The Journal of Chemical Thermodynamics, 76, 145–151. DOI: 10.1016/j. jct.2014.03.024.10.1016/j.jct.2014.03.024Search in Google Scholar

Bastl, Z., Senkevich, A. I., Spirovová, I., & Vrtílková, V. (2002). Angle-resolved core-level spectroscopy of Zr1Nb alloy oxidation by oxygen, water and hydrogen peroxide. Surface and Interface Analysis, 34, 477–480. DOI: 10.1002/sia.1342.10.1002/sia.1342Search in Google Scholar

Bernardet, V., Gomes, S., Delpeux, S., Dubois, M., Guérin, K., Avignant, D., Renaudin, G., & Duclaux, L. (2009). Protection of nuclear graphite toward fluoride molten salt by glassy carbon deposit. Journal of Nuclear Materials, 384, 292–302. DOI: 10.1016/j.jnucmat.2008.11.032.10.1016/j.jnucmat.2008.11.032Search in Google Scholar

Boča, M., Danielik, V., Ivanová, Z., Mikšíková, E., & Kubíková, B. (2007). Phase diagrams of the KF-K₂TaF₇ and KF-Ta₂O₅ systems. Journal of Thermal Analysis and Calorimetry, 90, 159–165. DOI: 10.1007/s10973-006-7700-5.10.1007/s10973-006-7700-5Search in Google Scholar

Cox, B. (2005). Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys. Journal of Nuclear Materials, 336, 331–368. DOI: 10.1016/j.jnucmat.2004.09.029.10.1016/j.jnucmat.2004.09.029Search in Google Scholar

Danielik, V., Fellner, P., & Matal, O. (2009). Corrosion of nickel in the molten mixture LiF-NaF-ZrF₄. Acta Chim Slovaca, 2, 3–11.Search in Google Scholar

El-Rahman, H. A. A., Baraka, A. M., Morsi, M. S., & El-Gwad, S. A. A. (1994). Role of oxide-ion concentration on the oxidation behavior of zirconium in molten NaNO₃-KNO₃ eutectic. Thin Solid Films, 247, 56–63. DOI: 10.1016/0040-6090(94)90476-6.10.1016/0040-6090(94)90476-6Search in Google Scholar

Ghosh, S., Vandarkuzhah, S., Venkatesh, P., Seenivasan, G., Subramanian, T., Reddy, B. P., & Nagarajan, K. (2009). Electrochemical studies on the redox behaviour of zirconium in molten LiCl–KCl eutectic. Journal of Electroanalytical Chemistry, 627, 15–27. DOI: 10.1016/j.jelechem.2008.12.011.10.1016/j.jelechem.2008.12.011Search in Google Scholar

Gil, A., Medrano, M., Martorell, I., Lázaro, A., Dolado, P., Zalba, B., & Cabeza, L. F. (2010). State of the art on high temperature thermal energy storage for power generation. Part 1—Concepts, materials and modellization. Renewable & Sustainable Energy Reviews, 14, 31–55. DOI: 10.1016/j.rser.2009.07.035.10.1016/j.rser.2009.07.035Search in Google Scholar

Guillot, S., Faik, A., Rakhmatullin, A., Lambert, J., Veron, E., Echegut, P., Bessada, C., Calvet, N., & Py, X. (2012). Corrosion effects between molten salts and thermal storage material for concentrated solar power plants. Applied Energy, 94, 174–181. DOI: 10.1016/j.apenergy.2011.12.057.10.1016/j.apenergy.2011.12.057Search in Google Scholar

Kim, Y. E., Park, J. W., & Cleveland, J. (2006). Thermophysical properties database of materials for light water reactors and heavy water reactors. Vienna, Austria: International Atomic Energy Agency.Search in Google Scholar

Krýsa, J., Maixner, J., Matějka, P., & Vrtílková, V. (2000). Structure and composition of zirconium oxide films formed in high pressure water with different Li⁺ concentration at 360°C. Materials Chemistry and Physics, 63, 1–8. DOI: 10.1016/s0254-0584(99)00180-7.10.1016/s0254-0584(99)00180-7Search in Google Scholar

Kubíková, B., Macková, I., & Boča, M. (2013). Phase analysis and volume properties of the (LiF–NaF–KF)_eut-K₂ZrF₆ system. Monatshefte für Chemie – Chemical Monthly, 144, 295–300. DOI: 10.1007/s00706-012-0886-2.10.1007/s00706-012-0886-2Search in Google Scholar

Kutty, T. R. G., Ravi, K., & Ganguly, C. (1999). Studies on hot hardness of Zr and its alloys for nuclear reactors. Journal of Nuclear Materials, 265, 91–99. DOI: 10.1016/s0022-3115(98)00610-2.10.1016/s0022-3115(98)00610-2Search in Google Scholar

Kwon, O. H., Eom, K. B., Kim, J. I., Suh, J. M., & Jeon, K. L. (2011). Mechanical and irradiation properties of zirconium alloys irradiated in hanaro. Nuclear Engineering and Technology, 43, 19–24. DOI: 10.5516/net.2011.43.1.019.10.5516/net.2011.43.1.019Search in Google Scholar

Marcus, P. (2002). Corrosion mechanisms in theory and practice (2nd ed.). New York, NY, USA: Marcel–Dekker.10.1201/9780203909188Search in Google Scholar

McDeavitt, S. M., Abraham, D. P., Park, J. Y., & Keiser, D. D., Jr. (1997). Stainless steel-zirconium waste forms from the treatment of spent nuclear fuel. The Journal of the Minerals, Metals & Materials Society (TMS), 49, 29–32. DOI: 10.1007/bf02914763.10.1007/bf02914763Search in Google Scholar

Medrano, M., Gil, A., Martorell, I., Potau, X., & Cabeza, L. F. (2010). State of the art on high-temperature thermal energy storage for power generation. Part 2—Case studies. Renewable and Sustainable Energy Reviews, 14, 56–72. DOI: 10.1016/j.rser.2009.07.036.10.1016/j.rser.2009.07.036Search in Google Scholar

Netriová, Z., Boča, M., Danielik, V., & Mikšíková, E. (2009). Phase diagram of the system KF-K₂TaF₇-Ta₂O₅. Journal of Thermal Analysis and Calorimetry, 95, 111–115. DOI: 10.1007/s10973-008-9063-6.10.1007/s10973-008-9063-6Search in Google Scholar

Northwood, D. O. (1985). The development and applications of zirconium alloys. Materials & Design, 6, 58–70. DOI: 10.1016/0261-3069(85)90165-7.10.1016/0261-3069(85)90165-7Search in Google Scholar

Olson, L. C., Ambrosek, J. W., Sridharan, K., Anderson, M. H., & Allen, T. R. (2009). Materials corrosion in molten LiF– NaF–KF salt. Journal of Fluorine Chemistry, 130, 67–73. DOI: 10.1016/j.jfluchem.2008.05.008.10.1016/j.jfluchem.2008.05.008Search in Google Scholar

Pavlík, V., & Boča, M. (2012). Corrosion of titanium diboride in molten FLiNaK_(eut). Chemical Papers, 66, 1073–1077. DOI: 10.2478/s11696-012-0202-y.10.2478/s11696-012-0202-ySearch in Google Scholar

Podor, R., David, N., Rapin, C., Vilasi, M., & Berthod, P. (2007). Mechanisms of corrosion layer formation during zirconium immersion in a (Fe)-bearing glass melt. Corrosion Science, 49, 3226–3240. DOI: 10.1016/j.corsci.2007.03.005.10.1016/j.corsci.2007.03.005Search in Google Scholar

Rudling, P., Strasser, A., & Garzarolli, F. (2007). Welding of zirconium alloys. Skultuna, Sweden: Advanced Nuclear Technology International.Search in Google Scholar

Salanne, M., Simon, C., Turq, P., & Madden, P. A. (2009). Heat-transport properties of molten fluorides: Determination from first-principles. Journal of Fluorine Chemistry, 130, 38– 44. DOI: 10.1016/j.jfluchem.2008.07.013.10.1016/j.jfluchem.2008.07.013Search in Google Scholar

Shankar, A. R., Raju, V. R., Rao, M. N., Mudali, U. K., Khatak, H. S., & Raj, B. (2007). Corrosion of Zircaloy-4 and its welds in nitric acid medium. Corrosion Science, 49, 3527–3538. DOI: 10.1016/j.corsci.2007.03.029.10.1016/j.corsci.2007.03.029Search in Google Scholar