| Zircaloys are commonly used as cladding materials for fuel rods and core structure materials in nuclear water reactors and nuclear power submarines. The zirconium-based alloys are under the conditions of high-temperature, high-pressured, high irradiation flux and highly pure water, therefore the studies about the corrosion and oxidation behaviors of zircaloys become one of the hotspots in the field of nuclear materials. The concepts of high burn-up, long duration time and zero broken were putted forward, which made improving the corrosion resistance and anti-high temperature oxidation behavior of zircaloys are very important in the ranges of subject, economy and safety.In order to investigate systemically the influence of ion implantation on the corrosion and oxidation behavior of zirconium and zircaloy-4, specimens were implanted with all kinds of ions using MEVVA source implantor. The irradiated ions included rare-earth elements, such as yttrium, lanthanum, cerium, zirconium self ion and alloy elements of zircaloy-4 such as chromium, nickel, tin, metal element with high melted-point temperature such as molybdenum, and inert gas element such as krypton ions. The main innovative results are below: ①The corrosion behavior of zirconium specimen implanted by yttrium with low fluence is increased, while the corrosion resistance of zirconium samples implanted by yttrium with high fluences is improved. The reasons are attributed to the surface damage resulted from ions implantation and the protection of Y2O3. ②The corrosion resistance of zirconium samples implanted by lanthanum is improved. The higher the fluence, the better the corrosion resistance. The main reason is the concentration of the oxide La2O3 as a barrier increases with increasing the fluences. The oxidation resistance of zircaloys is improved by lanthanum ion implantation; it is believed that the oxide film in the surface of zircaloys changed from loose monoclinic zirconia to compact tetragonal zirconia.③The cerium exists in two forms of CeO2 and CeH3 when the cerium ions were implanted into zircaloys. The corrosion behavior of zirconium samples implanted by cerium is increased, while the corrosion resistance of zircaloy-4 implanted by cerium is improved. The reason is the CeH3 can promote the anodic reactions.④The corrosion resistance of zirconium samples implanted by chromium is improved. The corrosion resistance of zircaloy-4 samples implanted by chromium with low fluences is improved. This is attributed to the influences of oxidation protection and irradiation damage.The corrosion behavior of zirconium samples implanted by nickel is increased. The corrosion resistance of zircaloy-4 samples implanted by nickel with low fluence is improved, while when the fluence is high, the corrosion behavior of implanted samples increased. This is attributed to the influences of barrier Ni2O3, active Ni, oxidation protection and irradiation damage. The corrosion resistance of zircaloys implanted by tin with low fluence is improved, while when the fluences is high, the corrosion behavior of implanted samples increased, and many small tin balls were brought out under this condition.⑤The molybdenum exists in two forms of Mo and MoO3 when the molybdenum is implanted into zircaloys. The corrosion behavior of zirconium samples implanted by molybdenum is increased. The corrosion resistance of zircaloy-4 implanted by molybdenum with low fluence is improved, while when the fluence is high, the corrosion resistance of implanted zircaloy-4 samples declined. This is attributed to the influences of barrier MoO3, active Mo, oxidation protection and irradiation damage. The high-temperature oxide behavior of zircloy samples implanted by molybdenum is declined. The reasons is that MoO3 is easy to volatilize.⑥The corrosion resistance of zirconium samples subjected to self-ion bombardment dropped at first, then raised and dropped again. This is attributed to the influences of oxidation protection and irradiation. It is indicated that there is some relationship b...
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