摘要:
An alloy having a formula Zr100-x-u (Cu100-aNia)xAlu wherein X, U and a are in atomic percentages wherein X is less than or equal to 48 and greater than or equal to 37, wherein U is less than or equal to 14 and greater than or equal to 3, and wherein a is less than or equal to ten and greater than or equal to 3. Methods of forming the alloy and bulk metallic glass comprising the alloy are also provided. The alloy and bulk metallic glass are useful in a wide number of applications which includes sports and luxury products, electronic goods, medical instruments, and military equipment.
摘要:
A composition includes an alloy that has, by weight, 25-65% zirconium, 25-65% tungsten, and 6-25% of a combined amount of nickel in at least one of iron and cobalt. The alloy may be formed into a geometric body that has a density of 7.8 grams per cubic centimeter to 11.4 grams per cubic centimeter.
摘要:
Various embodiments of zirconium based bulk metallic glass with hafnium are described herein. In one embodiment, an alloy composition includes zirconium (Zr), hafnium (Hf), copper (Cu), aluminum (Al), at least one element from a group consisting of niobium (Nb) and titanium (Ti), and at least one element from a group consisting of nickel (Ni), iron (Fe), and cobalt (Co).
摘要:
Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The total amount of the niobium, the iron and the chromium is 1.1 to 1.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic feasibility and safety.
摘要:
Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in reactor accident conditions, a zirconium alloy nuclear fuel cladding prepared by using thereof and a method of preparing the same. The zirconium alloy includes 1.0 to 1.2 wt % of niobium (Nb); at least one element selected from tin (Sn), iron (Fe) and chromium (Cr); 0.02 to 0.1 wt % of copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Sn is 0.1 to 0.3 wt %, the amount of Fe is 0.3 to 0.8 wt %, and the amount of Cr is 0.1 to 0.3 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic efficiency and safety.
摘要:
Identifying a stable phase of a binary alloy comprising a solute element and a solvent element. In one example, at least two thermodynamic parameters associated with grain growth and phase separation of the binary alloy are determined, and the stable phase of the binary alloy is identified based on the first thermodynamic parameter and the second thermodynamic parameter, wherein the stable phase is one of a stable nanocrystalline phase, a metastable nanocrystalline phase, and a non-nanocrystalline phase.
摘要:
Alloys and methods for preparing the same are provided. The alloys are represented by the general formula of (ZraAlbCucNid)100-e-fYeMf, wherein a, b, c, and d are atomic fractions, in which: 0.472≦a≦0.568; 0.09≦b≦0.11; 0.27≦c≦0.33; 0.072≦d≦0.088; the sum of a, b, c, and d equals 1; e and f are atomic numbers of elements Y and M respectively, in which 0≦e≦5 and 0.01≦f≦5; and M is selected from the group consisting of Nb, Ta, Sc, and combinations thereof.
摘要:
The present invention provides a composition for collecting a metal component from a metal component-containing material, the composition containing a compound containing at least one element selected from the group consisting of lanthanoid elements and elements in group 2 of the periodic table, and a compound containing at least one element selected from the group consisting of elements in groups 3, 4, 12, and 13 of the periodic table and transition metal elements in the 4th period of the periodic table. The present invention further provides a method for collecting a metal component using this composition. With the use of the composition of the present invention, a metal component can be easily and efficiently collected from a material containing a highly useful metal component such as noble or rare metal.
摘要:
A zirconium alloy that is resistant to shadow corrosion for a boiling water nuclear reactor fuel assembly component, the alloy being characterized in that: its composition in percentages by weight is as follows: Nb=0.4%-4.5% Sn=0.20%-1.7% Fe=0.05%-0.45% Fe+Cr+Ni+V=0.05%-0.45%, with Nb≦9×[0.5−(Fe+Cr+V+Ni)] S=traces-400 ppm C=traces-200 ppm Si=traces-120 ppm O=600 ppm-1800 ppm the balance being Zr and impurities from processing; in that, during fabrication, after its last hot deformation, it is subjected to one or more heat treatments lying in the range 450° C. to 610° C. for a total duration of at least 4 h, with at least one cold rolling operation with a rolling ratio of at least 25%; and in that a final heat treatment operation is performed at a temperature in the range 450° C. to 610° C. for 1 minute to 20 hours. A fuel assembly component made of the alloy, a fuel assembly including the component, and the use thereof.
摘要翻译:一种耐沸水核反应堆燃料组合部件的阴影腐蚀的锆合金,其特征在于:其重量百分比的组成如下:Nb = 0.4%-4.5%Sn = 0.20%-1.7% Fe + Cr + Ni + V = 0.05%-0.45%,Nb≦̸ 9×[0.5-(Fe + Cr + V + Ni)] S =痕量-400ppm C =痕量-200 ppm Si =痕量-1200ppm O = 600ppm-1800ppm余量为Zr和加工中的杂质; 因为在制造过程中,在其最后的热变形之后,在450℃至610℃的范围内对其进行一次或多次热处理,持续时间为至少4小时,至少一次冷轧 滚动比至少为25%的操作; 并且在450℃至610℃的温度下进行1分钟至20小时的最终热处理操作。 由合金制成的燃料组件部件,包括该部件的燃料组件及其用途。
摘要:
A coating process for the interior of a pipework system, which includes a subsystem having a first part-system and a second part-system coupled to the first part-system, wherein the part-system can be pressurized by a pressure difference via a first connection of the first part-system and via a second connection of the second part-system, and wherein the first connection of the second part-system is identical to the second connection of the first part-system. In a second process step the first part-system is pressurized in such a way that a fluid-flow of the coating material is established through the first part-system and then the first connection of the second part-system is pressurized after the coating material leaves the second connection of the first part-system so that the first part-system and the second part-system is consecutively fed with the coating material.