Journal articles: 'Zirconium alloys – Corrosion'

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Motta, Arthur T. "Waterside corrosion in zirconium alloys." JOM 63, no. 8 (August 2011): 59–63. http://dx.doi.org/10.1007/s11837-011-0140-0.

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Cox, B. "Stress corrosion cracking of zirconium alloys." Langmuir 3, no. 6 (November 1987): 867–73. http://dx.doi.org/10.1021/la00078a002.

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Kim, Minsuk, Seongbin An, Chaeeul Huh, and Chungseok Kim. "Development of Zirconium-Based Alloys with Low Elastic Modulus for Dental Implant Materials." Applied Sciences 9, no. 24 (December 4, 2019): 5281. http://dx.doi.org/10.3390/app9245281.

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The stress-shielding effect is a phenomenon in which the mutual coupling between bones and bio-materials of the human body is loosened due to the difference in elastic modulus, and bone absorption occurs due to the difference in density, which causes a shortening of the life of the material. The purpose of this study is to develop a zirconium-based alloy with low modulus and to prevent the stress-shielding effect. Zr–7Cu–xSn (x = 1, 5, 10, 15 mass%) alloys were prepared by an arc-melting process of pure zirconium, oxygen-free copper, and tin, respectively. The Zr–7Cu–xSn alloy has two phase α-Zr and Zr2Cu intermetallic compounds. Microstructure characterization was analyzed by microscopy and X-ray diffraction. Corrosion tests of zirconium-based alloys were conducted through polarization tests, and zirconium-based alloys had better corrosion characteristics than other metal bio-materials. In general, the elastic modulus value (14–25 GPa) of the zirconium-based alloy is very similar to the elastic modulus value (15–30 GPa) of the human bone. Consequently, the zirconium-based alloy is likely to be used as a bio-material that negates the effect of stress shielding on human bones.

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dos Santos, Demetrio Jackson, Lara Basilio Tavares, and Maria Cecilia Salvadori. "Zirconium Based Metal Pretreatments: A Characterization Method for Ecologically Sustainable Thin Film Surface Pretreatments." Materials Science Forum 869 (August 2016): 693–98. http://dx.doi.org/10.4028/www.scientific.net/msf.869.693.

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Zirconium based metal pretreatments have become widely used in recent years as a substitute for phosphate deposition on steel alloys and for chromate on aluminum alloys in industrial applications. The choice of a zirconium based intermediate layer follows from its ecologic sustainability − decreased water and energy consumption, vehicle weight reduction, and low byproduct generation during processing. Here we describe our investigations of a characterization method of converted metal oxide thin films deposited by a plasma method. The thin film composition was characterized by Rutherford Backscattering Spectroscopy (RBS) and Energy Dispersive Spectroscopy (EDS) before and after conversion by a zirconium-based pretreatment, revealing the formation of zirconia after treatment. The corrosion mechanism of the deposited metal oxide films was investigated using electrochemical analysis, confirming the susceptibility of the film to corrosion and the applicability of corrosion investigations. The results pointed to a better performance of the RBS in comparison to EDS.

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Mousavian, Seyed Mohammad Hossein, Seyed Hadi Tabaian, and Mohammadhassan Badihehaghdam. "Effects of zirconium addition on electrochemical and mechanical properties of Mg-3Zn-1Ca-1RE alloy." Anti-Corrosion Methods and Materials 67, no. 6 (November 26, 2020): 583–91. http://dx.doi.org/10.1108/acmm-06-2020-2324.

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Purpose The effect of zirconium, zinc, calcium and rare earth group as the alloying elements on mechanical properties and corrosion behavior of magnesium alloys was investigated in the simulated body fluid. Design/methodology/approach Pure magnesium and the alloying elements were melted and zirconium was finally added to obtain different alloys. The castings were annealed and some samples were aged heat treated. X-ray fluorescence was used for the elemental analysis and LSV was used for electrochemical corrosion evaluations. Findings Results showed that corrosion resistance decreases with increasing zirconium content. The lowest corrosion rate was obtained for the samples containing 0.3% and 0.45% of Zr from annealed and aging heat-treated samples, respectively. Yield stress enhances with increasing the zirconium content and degrades by the aging heat treatment. Originality/value These alloys were studied for the first time. Effect of casting without using protective flux and vacuum furnaces. Effect of annealing at 440°C for 2 h and artificial aging at 200°C for 16 h. Alloy’s electrochemical behavior on the body’s simulation environment has been investigated. Improvement of mechanical properties after annealing heat treatment by high zirconium percentage.

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Zhang, Jun Song, Chong Sheng Long, Jing Jing Liao, Tian Guo Wei, and Zhong Bo Yang. "Deoxidation Process of Oxidized Zirconium Alloy." Materials Science Forum 993 (May 2020): 22–28. http://dx.doi.org/10.4028/www.scientific.net/msf.993.22.

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When zirconium alloy is corroded, an oxide film is formed on the surface, which hinders the ion transfer during the corrosion process. Therefore, the analysis of the oxide film is an important part of the research on the corrosion resistance of zirconium alloys. In this paper, two kinds of Zr-Sn-Nb alloys were corroded in 400 °C/10.3 MPa pure steam and 500 °C/10.3 MPa pure steam in autoclave to obtain samples with oxide thickness of 14 um and 18 um respectively. Then they were annealed at 800 °C at a pressure of 10-4 Pa for 18 h. XRD and WDS studies were used to analyze the structure and oxygen content of the oxide film after annealing. The results indicate that the oxide films of alloys change from zirconium dioxide to zirconium after annealing. The oxygen diffuses into the substrate and its content decreases continuously with increasing diffusion distance. Combined with the SEM analysis of cross-section samples, it is found that the annealed samples are composed of several layers. An oxygen-saturated zirconium layer, a transitional layer with micro-cracks, an oxygen-dissolved α-Zr layer and a β-Zr layer are identified. Based on these results, the mechanism of the ion transfer in the oxide film during annealing is analyzed deeply. It is proposed that space charges in the oxide film have a major impact on deoxidation kinetics. This study provides a new research method for the corrosion mechanism of zirconium alloys.

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Jithendra Kumar, Repalle, B. V. S. Raghu Vamsi, T. Siva Krishna, D. Tarun, and M. Kamal Tej. "Evaluation of Coefficient of Thermal Expansion of Zirconium by Using Dilatometer & Ansys." Advanced Materials Research 1148 (June 2018): 128–35. http://dx.doi.org/10.4028/www.scientific.net/amr.1148.128.

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Zirconium alloys are solid solutions of zirconium or other metals. Zirconium has very low absorption cross-section of thermal neutrons. Zirconium has high corrosion resistance, ductility and hardness. Zirconium is mainly used as a good refractory metal. Zirconium can be manufactured by using standard fabrication techniques. In the present scenario zirconium alloys are used in water reactors for the cladding of fuel rods in nuclear reactors in nuclear technology. We use the composition of zirconium alloys as more than 94.5 weight percentage of zirconium and less than 2.45 weight percentage of copper which are added to improve mechanical, thermal properties and corrosion resistance. This paper first focuses on the study of thermal properties of Zirconium. And this particularly concentrated on variation of Coefficient of Thermal Expansion by varying temperatures by using Dilatometer and as well as ANSYS

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Preuss, M., P. Frankel, S. Lozano-Perez, D. Hudson, E. Polatidis, N. Ni, J. Wei, et al. "Studies Regarding Corrosion Mechanisms in Zirconium Alloys." Journal of ASTM International 8, no. 9 (2011): 103246. http://dx.doi.org/10.1520/jai103246.

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Tsutsumi, Yusuke, Yousuke Takano, Hisashi Doi, Kazuhiko Noda, and Takao Hanawa. "Corrosion Behavior of Zirconium Based Alloys in Simulated Body Fluids." Materials Science Forum 561-565 (October 2007): 1489–92. http://dx.doi.org/10.4028/www.scientific.net/msf.561-565.1489.

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The corrosion behavior of Zr-Ti and Zr-Hf alloys with various concentrations in properly deaerated Hanks’ solution were investigated by electrochemical techniques. The effects of the thermal treatment with the purpose of homogenization of chemical composition on the pitting potentials of the Zr-Ti alloys were also examined. The results indicated that sufficient addition of Ti to Zr improved its corrosion resistance, especially in terms of the pitting potential and the passive current density. On the other hand, addition of Hf totally lowered the corrosion resistance of the alloy. The thermal treatment improved the pitting corrosion property of Zr-Ti alloys, and Zr alloys with over 5mol% Ti showed much higher pitting potentials than that of pure Zr. The treatment also improved the reproducibility of the measurement and narrowed the data scattering. This phenomenon was discussed with the model of rapidly-cooled metallographic structure.

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Luo, J. S., and D. P. Abraham. "Transmission Electron Microscopy of Corrosion of Stainless Steel-Zirconium Metal Waste Forms." Microscopy and Microanalysis 5, S2 (August 1999): 848–49. http://dx.doi.org/10.1017/s1431927600017566.

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Stainless steel-zirconium (SS-Zr) alloys have been developed as waste forms to immobilize and retain fission products generated during the electrometallurgical treatment of spent nuclear fuel. The baseline waste form is a stainless steel-15 wt.% zirconium (SS-15Zr) alloy, which is prepared by melting appropriate amount of Type 316 stainless steel (SS316) and high purity zirconium. As zirconium has very low solubility in iron, the addition of zirconium to SS316 results in the formation of ZrFe2 -type Laves intermetallic phases. The corrosion behavior of stainless steel has been widely studied; however, the corrosion behavior of the Zr-based-intermetallic has not been previously investigated. In this paper, we present a microstructural characterization of the corrosion layer formed on the Zr-intermetallic phase using energy-filtering transmission electron microscopy (TEM) and energy dispersive x-ray spectroscopy (EDS).Specimens of SS-15Zr alloy, crushed to 75 to 150 μm sizes, were immersed in 90°C deionized water for a period of two years.

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Rawers, J., W. Reitz, S. Bullard, and E. K. Roub. "Surface and Corrosion Study of Laser-Processed Zirconium Alloys." Corrosion 47, no. 10 (October 1, 1991): 769–77. http://dx.doi.org/10.5006/1.3585187.

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Abstract Reactor Grade Zirconium (Zircaloy-2) was laser-glazed and laser-alloyed with nickel (Ni) or chromium (Cr) powders. Laser alloying produced a surface that was macroscopically, chemically homogeneous. However, at the microscopic level the melt zone was a mixture of microcrystalline pure zirconium (Zr) and extremely fine grain, or possibly amorphous, solid solution regions of Zr and alloying elements. Corrosion tests (potentiodynamic and long-term immersion) were conducted in 10% FeCl3 solution. The potentiodynamic tests showed icorr and Ecorr were a strong function of surface conditioning, altered by grit-blasting, laser processing, acid cleaning, and heat treating. Significant improvement was achieved in corrosion resistance by laser-glazing and laser-alloying.

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Souza, Armando Cirilo, J. L. Rossi, P. Tsakiropoulos, L. G. Martinez, Carlos Roberto Grandini, F. C. Ceoni, C. S. Mucsi, and H. P. S. Correa. "Preparation and Melting of Zr-1.0Nb Alloy." Materials Science Forum 869 (August 2016): 578–84. http://dx.doi.org/10.4028/www.scientific.net/msf.869.578.

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Zirconium alloys have many applications in industry in services too harsh for stainless steels, nickel alloys or where a noteworthy improvement in service life may be achieved, by choosing zirconium alloys instead of other metals, such as high permeability to thermal neutrons and excellent corrosion resistance in nuclear reactor environments. Mixing alloying elements, such as niobium, molybdenum, tin, titanium and tantalum, with zirconium changes its physical and chemical properties, especially its resistance to corrosion. In this study, specimens of Zr-1.0Nb alloy were obtained by melting in a furnace with non-consumable electrodes in argon atmosphere. Different samples were prepared to ensure good homogeneity of the specimens. The melting procedure was tested several times to determine the parameters that ensure proper alloy handling. These parameters include the melting point of the alloys under pressure and the current in the furnace. Using the derived melting parameters and processing parameters, it has been obtained Zr-1.0Nb alloy specimens with appropriate homogeneity, as confirmed by auxiliary characterization techniques, such as optical microscopy, scanning electron microscopy, energy dispersive spectroscopy and X-ray diffraction. For these methods, the requirements for physicochemical properties in the nuclear sector were incorporated into the analyses.

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Mayer, P., and A. V. Manolescu. "Corrosion of Zirconium Alloys in Alternating pH Environment." Canadian Metallurgical Quarterly 24, no. 3 (July 1985): 197–206. http://dx.doi.org/10.1179/cmq.1985.24.3.197.

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Liao, Jing Jing, Zhong Bo Yang, Shao Yu Qiu, Zheng Cao Li, and Qian Peng. "Corrosion Behavior and Oxide Films of New Zirconium Cladding Corroded at Different Conditions." Materials Science Forum 944 (January 2019): 480–87. http://dx.doi.org/10.4028/www.scientific.net/msf.944.480.

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Zirconium alloys are mostly served as the cladding materials in water reactors. Corrosion is one of the concerning problems in zirconium utilization. Transition of corrosion occurs every 2~3 μm in thickness, but its mechanism is not confirmed. To study the influence of water chemistry and the mechanism behind transition, a new type of zirconium cladding was tested for three corrosion conditions: the pure water, LiOH solution, LiOH/H3BO3 solution at 360°C/18.6MPa. For all cases, Zr-0.5Sn-0.15Nb-0.5Fe-0.2V cladding had a lower corrosion rate and a longer transition time than N36 cladding. The corrosion results showed that the corrosion rate was the highest and the transition time was the shortest in LiOH solution. Oxide phase information on the oxidized surface was obtained by Raman study. Tetragonal zirconia, embedded in the surface, was found at the beginning of corrosion. As the corrosion time increased, tetragonal phase stress was almost released and the content of tetragonal phase was also decreased to zero at the transition point. Stable tetragonal phase was found on the samples corroded in pure water. However, in LiOH solution, it was eliminated the quickest. The acceleration of transition in LiOH solution is partly resulted from the fast transformation of tetragonal phase. The reason for the longer transition time in N2 cladding can be directly attributed to the smaller decrease of the tetragonal phase.

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Nykyforchyn, H. M., V. S. Agarwala, M. D. Klapkiv, and V. M. Posuvailo. "Simultaneous Reduction of Wear and Corrosion of Titanium, Magnesium and Zirconium Alloys by Surface Plasma Electrolytic Oxidation Treatment." Advanced Materials Research 38 (March 2008): 27–35. http://dx.doi.org/10.4028/www.scientific.net/amr.38.27.

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Titanium, magnesium and zirconium alloys are widely used in industrial applications, which require high wear and corrosion resistance. However current methods of improving these properties often do not satisfy the requirements of service and functional properties. An alternative approach is the application of oxide-ceramic coatings using high temperature process. The coatings are applied by spark discharge plasma in the metal-electrolyte system at high voltages - PEO (plasma electrolytic oxidation) as an oxide synthesis method. This method has shown good results for aluminium alloys and with good prospects to be used for titanium, magnesium and zirconium alloys. Development of PEO technology to improve the wear and corrosion resistance of titanium, magnesium and zirconium alloys is discussed in this paper. It describes the methods for obtaining the required layer-thickness for a specified hardness, porosity, wear and corrosion resistance, sets up the optimal process parameters (voltage/current) by taking the relation of anodic to cathodic currents into account, and establishing the electrolyte content of different dopants.

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Patel, Mitesh, and Miles A. Stopher. "Hydrogen effects in non-ferrous alloys: discussion." Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 375, no. 2098 (June 12, 2017): 20170030. http://dx.doi.org/10.1098/rsta.2017.0030.

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This is a transcript of the discussion session on the effects of hydrogen in the non-ferrous alloys of zirconium and titanium, which are anisotropic hydride-forming metals. The four talks focus on the hydrogen embrittlement mechanisms that affect zirconium and titanium components, which are respectively used in the nuclear and aerospace industries. Two specific mechanisms are delayed hydride cracking and stress corrosion cracking. This article is part of the themed issue ‘The challenges of hydrogen and metals’.

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Kaiser, Mohammad Salim, Mohammad Abdul Matin, and Kazi Mohammad Shorowordi. "Role of magnesium and minor zirconium on the wear behavior of 5xxx series aluminum alloys under different environments." Journal of Mechanical and Energy Engineering 4, no. 3 (December 10, 2020): 209–20. http://dx.doi.org/10.30464/jmee.2020.4.3.209.

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The tribological performance of 5xxx series aluminum alloys with ternary zirconium is evaluated at ambient conditions under dry, wet and saline environment. The experiment has been done using a Pin-on-Disk apparatus under an applied load of 20N. The sliding distances varies ranging from 116m-2772m at a sliding velocity of 0.385 ms-1. The results show that presence of Mg and Zr into this alloy helps to increase their strength and wear resistance under dry sliding condition. But they significantly suffer under wet and corrosive environment due to formation of β-phase Al3Mg2, to slip bands and grain boundaries which may lead to and stress-corrosion cracking. The variation of friction coefficient is observed in wet and corrosive environment due to the formation of oxidation film, lubrication, and corrosion action in solution. The SEM fracture surface shows that brittle Al3Mg2 phase initiate the brittle fracture surface for Al-Mg alloy and Zr addition accelerate the brittleness of the alloy owing the fine precipitates of Al3Zr.

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Sialini, P., P. Sajdl, V. Havránek, and V. Vrtílková. "Study of diffusion processes in the oxide layer of zirconium alloys." Koroze a ochrana materialu 60, no. 1 (March 1, 2016): 1–5. http://dx.doi.org/10.1515/kom-2016-0004.

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Abstract In the active zone of a nuclear reactor where zirconium alloys are used as a coating material, this material is subject to various harmful impacts. During water decomposition reactions, hydrogen and oxygen are evolved that may diffuse through the oxidic layer either through zirconium dioxide (ZrO2) crystals or along ZrO2 grains. The diffusion mechanism can be studied using the Ion Beam Analysis (IBA) method where nuclear reaction 18O(p,α)15N is used. A tube made of zirconium alloy E110 (with 1 wt. % of Nb) was used for making samples that were pre-exposed in UJP PRAHA a.s. and subsequently exposed to isotopically cleansed environment of H2 18O medium in an autoclave. The samples were analysed with gravimetric methods and IBA methods performed at the electrostatic particle accelerator Tandetron 4130 MC in the Nucler Physics Institute of the CAS, Řež. With IBA methods, the overall thicknesses of corrosion layers on the samples, element composition of the alloy and distribution of oxygen isotope 18O in the corrosion layer and its penetration in the alloy were identified. The retrieved data shows at the oxygen diffusion along ZrO2 grains because there are two peaks of 18O isotope concentrations in the corrosion layer. These peaks occur at the environment-oxide and oxide-metal interface. The element analysis identified the presence of undesirable hafnium.

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Delijic, Kemal, Vanja Asanovic, and Dragan Radonjic. "Mechanical behavior and corrosion properties of some AA6xxx aluminum alloys in T5 temper." Chemical Industry and Chemical Engineering Quarterly 12, no. 4 (2006): 231–35. http://dx.doi.org/10.2298/ciceq0604231d.

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The paper describes the mechanical and corrosion properties of three heat treatable extruded Al-Mg-Si aluminum alloys. The alloys were tested as T5 tempered (air-quenched directly on the press and artificially aged) after processing by the extrusion of semi-continuous cast and homogenized billets. The addition of small amounts of zirconium and manganese in the base AIMgSiO.7 alloy increased the strength, reaching 310 MPa of tensile strength and increased the corrosion rate by 15% in aqueous sodium chloride solution.

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Kravchenko, V. V., and S. D. Tsygankova. "Effect of Corrosion of the Fuel Rod Construction Materials on the Radiation Safety of Nuclear Power Plants with PWR." ENERGETIKA. Proceedings of CIS higher education institutions and power engineering associations 63, no. 1 (February 7, 2020): 89–98. http://dx.doi.org/10.21122/1029-7448-2020-63-1-89-98.

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The article considers the general concept of corrosion in accordance with GOST 5272–68 “Metal Corrosion”, the classification of the corrosion process, the stages of corrosion as energy function of the flow path of the corrosion process, the main indicators of the corrosion process. According to the forecasts of the International Monetary Fund and Focus Economics, the amount of funds that will be spent on counteracting corrosion and its consequences in selected industrialized countries has been estimated. The growth of funds invested in the counteracting the effects of metal corrosion in the Russian Federation for 2016–2019 is presented in the form of a diagram. The substantiation of the use of zirconium as a structural material for the shell of fuel rods has been fulfilled. The values of the thermal neutron absorption cross sections for various elements serving as structural elements for the core of a nuclear reactor are presented. Factors influencing the choice of alloying elements and their percentage in various alloys (Zr-2, Zr-4, ZIRLO™, M5®), which are the special development that reduce the corrosion rate, are also considered. The composition and mechanical properties of E110 and E635 alloys, which were used as materials for the fuel rods shell in the core of WWER-1200 reactors at the Belarusian NPP, are considered as well. The behavior of zirconium alloys E110 and E635 in the core is analyzed. The main factors that make a significant contribution to the corrosion process in actual operating conditions of zirconium alloys as fuel rods shell have been identified. The existing methods of preliminary special processing of fuel rods shells stored in the air for a long time before their receipt for assembly are presented. The structure of the oxide on the shells of alloys E110 and E635 oxidized in an autoclave is demonstrated.

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Ramezani, Leila, Masoud Mansouri, and Mohammad Rahgoshay. "Modeling the water side corrosion and hydrogen pickup of VVER 1000 fuel clad." Nuclear Technology and Radiation Protection 33, no. 4 (2018): 334–40. http://dx.doi.org/10.2298/ntrp180606013r.

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Zirconium alloys, are usually used as fuel cladding materials in VVER (water-cooled, water-moderated energy reactor) type reactors, mainly, due to their low neutron absorption cross-section, desirable mechanical properties, and good corrosion resistance under reactor operating conditions. During exposure to water at high temperature, water reacts with zirconium alloys, which results in the production of an oxide layer. The entire area of corrosion along with the accompanying absorption of hydrogen in the zirconium metal matrix has attracted a lot of attention when the performance of the core components as well as the operation of the reactor is emphasized. The growth of the zirconium oxide layer plays a destructive role in decreasing thermal efficiency of the reactor by restricting the inlet temperature and chemical properties of the coolant. The present study aimed to develop a computer code to predict long-term water side corrosion weight gain, oxide thickness and determine the concentration of absorbed hydrogen in VVER-1000 reactors during normal operating conditions. The proposed model can be utilized to estimate the pre-transition and post-transition corrosion weight gain and the oxide thickness in operating conditions.

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Guerain, M., C. Duriez, J. L. Grosseau-Poussard, and M. Mermoux. "Review of stress fields in Zirconium alloys corrosion scales." Corrosion Science 95 (June 2015): 11–21. http://dx.doi.org/10.1016/j.corsci.2015.03.004.

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Müller, S., and L. Lanzani. "Corrosion of zirconium alloys in concentrated lithium hydroxide solutions." Journal of Nuclear Materials 439, no. 1-3 (August 2013): 251–57. http://dx.doi.org/10.1016/j.jnucmat.2012.07.030.

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Motta, Arthur T., Adrien Couet, and Robert J. Comstock. "Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding." Annual Review of Materials Research 45, no. 1 (July 2015): 311–43. http://dx.doi.org/10.1146/annurev-matsci-070214-020951.

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Renčiuková, Veronika, Jan Macák, Petr Sajdl, Radek Novotný, and Aneta Krausová. "Corrosion of zirconium alloys demonstrated by using impedance spectroscopy." Journal of Nuclear Materials 510 (November 2018): 312–21. http://dx.doi.org/10.1016/j.jnucmat.2018.08.005.

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GHOSAL, S. K., G. C. PALIT, and P. K. DE. "Corrosion of Zirconium Alloys in Nuclear Applications – A Review." Mineral Processing and Extractive Metallurgy Review 22, no. 4-6 (January 2002): 519–46. http://dx.doi.org/10.1080/08827500208547428.

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GHOSAL, S. K., G. C. PALIT, and P. K. DE. "Corrosion of Zirconium Alloys in Nuclear Applications - A Review." Mineral Processing and Extractive Metallurgy Review 22, no. 2 (January 2001): 519–46. http://dx.doi.org/10.1080/08827509808962514.

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Kamachi Mudali, U., S. Baunack, J. Eckert, L. Schultz, and A. Gebert. "Pitting corrosion of bulk glass-forming zirconium-based alloys." Journal of Alloys and Compounds 377, no. 1-2 (September 2004): 290–97. http://dx.doi.org/10.1016/j.jallcom.2004.01.043.

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Malakhova, �. K., A. N. Kuzyukov, and A. V. Meshcheryakov. "Corrosion resistance of zirconium alloys in acetic acid media." Chemical and Petroleum Engineering 31, no. 3 (March 1995): 183–85. http://dx.doi.org/10.1007/bf01149316.

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Kulakov, G. V., Y. V. Konovalov, A. A. Kosaurov, M. M. Peregud, V. Y. Shishin, and A. A. Sheldyakov. "Post-irradiation examinations of dispersion fuel rods with modified zirconium alloys claddings." Voprosy Materialovedeniya, no. 3(95) (January 10, 2019): 206–12. http://dx.doi.org/10.22349/1994-6716-2018-95-3-206-212.

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Modified zirconium alloys E635Mand E635opt based on E635 alloy (E635 was selected as master alloy) have been developed at Bochvar Institute. Fuel rods with such claddings were manufactured at Bochvar Institute and were irradiated at MIR reactor (SC RIAR, Dimitrovgrad). The results from the PIE performed at RIAR are presented. Such features of claddings as microstructures, corrosion resistance (width and structure of oxide), hydrogen contents, distribution of hydrides, mechanical properties were examined and discussed. Modifications of the alloy E635opt and E635M showed higher resistance to corrosion and hydrogen pick-up compared to the E635 alloy, while maintaining high strength and ductility. They have confirmed their prospects for use as cladding for fuel rods with enhanced characteristics.

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Zhang, Lina, Liang-Yu Chen, Cuihua Zhao, Yujing Liu, and Lai-Chang Zhang. "Calculation of Oxygen Diffusion Coefficients in Oxide Films Formed on Low-Temperature Annealed Zr Alloys and Their Related Corrosion Behavior." Metals 9, no. 8 (August 2, 2019): 850. http://dx.doi.org/10.3390/met9080850.

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The growth of oxide film, which results from the inward oxygen diffusion from a corrosive environment, is a critical consideration for the corrosion resistance of zirconium alloys. This work calculates the oxygen diffusion coefficients in the oxide films formed on zirconium alloys annealed at 400~500 °C and investigates the related corrosion behavior. The annealed samples have a close size for the second-phase particles but a distinctive hardness, indicating the difference in substrate conditions. The weight gain of all samples highly follows parabolic laws. The weight gain of the sample annealed at 400 °C has the fastest increase rate at the very beginning of the corrosion test, but its oxide film has the slowest growth rate as the corrosion proceeds. By contrast, the sample annealed at 500 °C shows the lowest weight gain but the highest corrosion rate constant. Such a corrosion behavior is attributed to the amount of defects existing in the oxide film formed on the annealed samples; fewer defects would provide a lower fraction of short-circuit diffusion in total diffusion, resulting in a lower diffusion coefficient of oxygen in the oxide film, thereby producing better corrosion resistance. This is consistent with the calculated diffusion coefficients of oxygen in the oxide films: 3.252 × 10−11 cm2/s, 3.464 × 10−11 cm2/s and 3.740 × 10−11 cm2/s for the samples annealed at 400 °C, 450 °C, and 500 °C, respectively.

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Hanlon, Sean, Scott Read, and Kevin McCaugherty. "ON THE DEVELOPMENT OF A NOVEL TECHNIQUE FOR HYDRIDING USING ZIRCONIUM HYDRIDE POWDER." CNL Nuclear Review 8, no. 2 (December 1, 2019): 131–43. http://dx.doi.org/10.12943/cnr.2018.00008.

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Zirconium alloys are of particular interest for applications within the nuclear industry given their low thermal neutron capture cross-section to strength ratios, adequate corrosion resistance, and high temperature stability. However, zirconium alloys are susceptible to hydrogen embrittlement, which limits the service lives of zirconium alloy components in reactor systems. Hydrogen charging, or hydriding, is a technique used to artificially age ex-service or as-received material to predetermined hydrogen concentrations for material testing on representative specimens. This study presents a thermo-mechanical approach to precision hydriding. Discussion on the development and commissioning of a suitable apparatus, called the Thermomechanical Hydrogen Ingression System (THIS), is provided. Hydriding results from commissioning as well as several repeatability tests are reported, which demonstrate the viability of the technique and equipment.

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Delijić, Kemal, and Boštjan Markoli. "The influence of the chemical composition and type of alloy on corrosion performances of some medium strength Al-Mg-Si series of alloys." Metallurgical and Materials Engineering 20, no. 2 (July 30, 2014): 131–40. http://dx.doi.org/10.5937/metmateng1402131d.

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The effect of the chemical composition, i.e. content of silicone (Si) and other alloying elements (Zr, Mn, etc) on the corrosion behaviour and mechanical properties of Al-Mg-Si (6xxx) type alloys was investigated in this paper. Open circuit corrosion potential (OCP) measurements, linear polarization and potentiodynamic anodic/cathodic polarization were employed in order to determine the corrosion behaviour of artificially aged Al-Mg-Si samples in the chloride ions containing aqueous corrosion solutions. The difference in OCPs for the tested 6xxx type alloys in relation to the standard AA1020 alloy was observed to be between 1-4%, except for the AlMg0.65Si0.76Zr0.1 alloy when the difference was 14% (about 100 mV). The presence of zirconium and manganese in AlMgSi0.7 base alloy, that contains small excess of Si, shifts the OCPs to more negative values for -15 mV (~2%) and -88 mV (~11%) in natural water and 0,51 mol NaCl, respectively. All the tested 6xxx type alloys, except AlMg0.7Si1.2Mn0.8, show almost the same corrosion rates and other corrosion characteristics in chloride solution, with mass loss per year between 2.3-3 g/m2 .

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Lee, Si-Young, Hyun-Jun Lee, Jong-Hee Baek, Sung Soo Park, and Jung Gu Lee. "Microstructural and Corrosion Properties of Ti-to-Zr Dissimilar Alloy Joints Brazed with a Zr-Ti-Cu-Ni Amorphous Filler Alloy." Metals 11, no. 2 (January 21, 2021): 192. http://dx.doi.org/10.3390/met11020192.

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Titanium and Zircaloy-4 dissimilar alloys were brazed with a zirconium-titanium-copper-nickel amorphous filler alloy, and the resulting joint structures as well as their corrosion properties were examined. The microstructure of the brazed joints was investigated according to brazing holding time at 850 °C, and the corrosion property was analyzed by potentiodynamic polarization. During brazing, joints were produced by diffusion-induced isothermal solidification of the molten filler alloy. At a relatively brief brazing holding time of 5 min, a large segregation zone consisting of an active α-phase and a nobler intermetallic phase was generated in the joint center, which suffered from micro-galvanic corrosion. The presence of alloyed titanium deteriorated the nobility of the α-zirconium phase near the joint and induced galvanic coupling with cathodic base metals, resulting in massive localized corrosion. This localized corrosion caused the pitting behavior at the applied potential of −51.1~187.5 mV during anodic polarization. With a brazing holding time of 20 min, the concentration of the alloying elements was homogenized to eliminate the electrochemical potential difference and minimize the galvanic corrosion susceptibility of the joint region. This homogeneous joint resulted in a highly passive corrosion behavior comparable to that of the titanium base metal.

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Yakushkin, A. A. "On the problems of creating shells of fuel rods from zirconium alloys for tolerant fuel." Physics and Chemistry of Materials Treatment 3 (2021): 69–78. http://dx.doi.org/10.30791/0015-3214-2021-3-69-78.

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Three directions of the establishment of accident tolerant fuel cladding for light water reactors are actively exploring at present: 1) replacement zirconium alloy E110 for more corrosion-resistant material in accident operation conditions; 2) surface dispersion hardening or doping of the zirconium cladding of fuel element; 3) deposition a corrosion-resistant coating to the fuel cladding. The first direction requires significant and irreversible changes in fuel rod production technology and has long-term prospects. Conversely, the second direction suggest minimal changes in the fuel rod production technology, however, it has no significant effect on the high temperature oxidation kinetics of fuel claddings in steam. Using of a corrosion resistant coating results in a significant change in the high temperature oxidation kinetics of the zirconium alloy, (no transition to linear oxidation) that is related to maintaining the continuity of the oxide layer formed during oxidation. The issue provides a brief overview of the current state of research in the field of fuel, tolerant to the effects of coolant in emergency situations.

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Cech, Miroslav, and Martin Sevecek. "MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION." Acta Polytechnica CTU Proceedings 4 (December 16, 2016): 13. http://dx.doi.org/10.14311/ap.2016.4.0013.

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This paper describes materials made of zirconium-based alloys used for nuclear fuel cladding fabrication. It is focused on corrosion problems their theoretical description and modeling in nuclear engineering.

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Yu, Sheng-xue, Rui-jun Zhang, Yong-fu Tang, Yan-ling Ma, and Wen-chao Du. "Composition and Performance of Nanostructured Zirconium Titanium Conversion Coating on Aluminum-Magnesium Alloys." Journal of Nanomaterials 2013 (2013): 1–8. http://dx.doi.org/10.1155/2013/594273.

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Nanostructured conversion coating of Al-Mg alloy was obtained via the surface treatment with zirconium titanium salt solution at 25°C for 10 min. The zirconium titanium salt solution is composed of tannic acid 1.00 g·L−1, K2ZrF60.75 g·L−1, NaF 1.25 g·L−1, MgSO41.0 g/L, and tetra-n-butyl titanate (TBT) 0.08 g·L−1. X-ray diffraction (XRD), X-ray photoelectron spectroscopy (XPS), and Fourier transform infrared spectrum (FT-IR) were used to characterize the composition and structure of the obtained conversion coating. The morphology of the conversion coating was obtained by atomic force microscopy (AFM) and scanning electron microscopy (SEM). Results exhibit that the zirconium titanium salt conversion coating of Al-Mg alloy contains Ti, Zr, Al, F, O, Mg, C, Na, and so on. The conversion coating with nm level thickness is smooth, uniform, and compact. Corrosion resistance of conversion coating was evaluated in the 3.5 wt.% NaCl electrolyte through polarization curves and electrochemical impedance spectrum (EIS). Self-corrosion current density on the nanostructured conversion coating of Al-Mg alloy is9.7×10-8A·cm-2, which is only 2% of that on the untreated aluminum-magnesium alloy. This result indicates that the corrosion resistance of the conversion coating is improved markedly after chemical conversion treatment.

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Kim, Yoon-Ho, Yong-Kyoon Mok, Hyun-Gil Kim, and Jong-Hyeon Lee. "Corrosion Behavior of Zirconium Alloys with Nb and Cr Addition." Korean Journal of Materials Research 25, no. 8 (August 31, 2015): 376–85. http://dx.doi.org/10.3740/mrsk.2015.25.8.376.

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Ji, R., X. Y. Li, and H. Dong. "Ceramic conversion treatment of zirconium alloys to combat corrosion wear." Surface Engineering 26, no. 1-2 (February 2010): 30–36. http://dx.doi.org/10.1179/026708409x12450792800079.

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Elmoselhi, MB, and A. Donner. "Inhibitors for Reducing Hydrogen Ingress During Corrosion of Zirconium Alloys." Journal of ASTM International 2, no. 4 (2005): 12422. http://dx.doi.org/10.1520/jai12422.

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Perekhozhev, V. I., L. P. Sinel'nikov, A. N. Timokhin, S. A. Averin, M. V. Chernetsov, and V. P. Kuznetsov. "Uniform and “Nodule” Corrosion of Zirconium Alloys under Service Conditions." Metal Science and Heat Treatment 45, no. 9/10 (September 2003): 390–95. http://dx.doi.org/10.1023/b:msat.0000009787.03101.93.

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OZAKI, Satoru. "The Mechanism of Localized In-pile Corrosion of Zirconium Alloys." Journal of Nuclear Science and Technology 35, no. 9 (September 1998): 654–61. http://dx.doi.org/10.1080/18811248.1998.9733921.

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Likhanskii, V. V., I. A. Evdokimov, T. N. Aliev, V. F. Kon’kov, V. A. Markelov, V. V. Novikov, and T. N. Khokhunova. "Corrosion Model for Zirconium-Niobium Alloys in Pressurized Water Reactors." Atomic Energy 116, no. 3 (June 22, 2014): 186–93. http://dx.doi.org/10.1007/s10512-014-9839-7.

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Cox, B. "Effects of palladium on the corrosion resistance of zirconium alloys." Journal of Nuclear Materials 211, no. 3 (August 1994): 256–58. http://dx.doi.org/10.1016/0022-3115(94)90356-5.

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Kakiuchi, Kazuo, Kazutoshi Okubo, Noboru Itagaki, Akihiro Miyazaki, Yoshiaki Ishii, Shunichi Suzuki, Takayuki Terai, and Michio Yamawaki. "Reducing Hydrogen Penetration through Corrosion Layer Formed on Zirconium Alloys by Iron Addition." Advances in Science and Technology 45 (October 2006): 1980–85. http://dx.doi.org/10.4028/www.scientific.net/ast.45.1980.

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Latest post-irradiation experiment results of Zry-2 and HiFi alloy (0.4%Fe-Zry2) showed that iron addition reduces the hydrogen pickup by these alloys compared to oxidation amount. In order to clarify the mechanism of reduced hydrogen absorption rate, (1) autoclave test, (2) surface potential measurement and (3) hydrogen absorption test of the intermetallic compound were carried out. Based on these results, a tentative mechanism for hydrogen absorption by zirconium alloys is proposed, taking into account of both the electrical potential gradient over the oxide film as well as the SPP window for hydrogen absorption.

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Andreeva, V. V., and A. I. Glukhova. "Corrosion and electrochemical properties of titanium, zirconium and titanium-zirconium alloys in acid solutions. II." Journal of Applied Chemistry 12, no. 10 (May 4, 2007): 457–68. http://dx.doi.org/10.1002/jctb.5010121006.

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Wang, Xiaobo, Zhipeng Li, Wen Zhan, Jesong Tu, Xiaohua Zuo, Xiangyi Deng, and Boyi Gui. "Preparation and corrosion resistance of titanium-zirconium/nickel-coated carbon nanotubes chemical nano-composite conversion coatings." Anti-Corrosion Methods and Materials 66, no. 3 (May 7, 2019): 343–51. http://dx.doi.org/10.1108/acmm-10-2018-2011.

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Purpose This study aims to expand the reliability and special functions of lightweight materials for high-end equipment and green manufacturing, so that it is the first such research to carry out nano-composite technology of nickel-coated carbon nanotubes (Ni-CNTs)-based titanium-zirconium chemical conversion on aluminum alloy substrate. Design/methodology/approach Corrosion behavior of various coatings was investigated using dropping corrosion test, linear polarization and electrochemical impedance spectroscopy. The results showed that the corrosion resistance of the nano-composite conversion coatings was significantly improved to compare with the conventional titanium-zirconium conversion coating. The morphology and microdomain characteristics of the nano-composite conversion coatings were characterized by SEM/eds/EPMA, which indicated that the CNT or Ni-CNTs addition promoting the integrity coverage of coatings in a short time. Findings Surface morphology of titanium-zirconium (Ti-Zr)/Ni-CNT specimens exhibited smooth, compact and little pores. The nano-composite conversion coatings are mainly composed of Al, O, C and Ti elements and contain a small amount of F and Zr elements, which illuminated that CNT or Ni-CNT addition could co-deposit with aluminum and titanium metal oxides. Originality/value The study of corrosion resistance of nano-composite conversion coatings and the micro-zone film-formation characteristics would be provided theoretical support for the development of basic research on surface treatment of aluminum alloys.

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Nikitin, K. N., and V. N. Shishov. "Behavior of a barrier layer of corrosion films on zirconium alloys." Protection of Metals and Physical Chemistry of Surfaces 46, no. 2 (March 2010): 261–66. http://dx.doi.org/10.1134/s2070205110020140.

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Vermoyal, J. J., A. Frichet, L. Dessemond, and A. Hammou. "AC impedance study of corrosion films formed on zirconium based alloys." Electrochimica Acta 45, no. 7 (December 1999): 1039–48. http://dx.doi.org/10.1016/s0013-4686(99)00307-2.

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OZAKI, Satoru. "The Mechanism of Localized In-pile Corrosion of Zirconium Alloys, (II)." Journal of Nuclear Science and Technology 36, no. 7 (July 1999): 605–12. http://dx.doi.org/10.1080/18811248.1999.9726244.

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Journal articles on the topic 'Zirconium alloys – Corrosion'

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