Abstract: A method for manufacturing a quasicrystal and alumina mixture particles reinforced magnesium matrix composite, includes manufacturing a quasicrystal and alumina mixture particles reinforcement phase, including preparing raw materials for the quasicrystal and alumina mixture particles reinforcement phase including a pure magnesium ingot, a pure zinc ingot, a magnesium-yttrium alloy in which the content of yttrium is 25% by weight, and nanometer alumina particles, the elements having the following proportion by weight 40 parts of magnesium, 50-60 parts of zinc, 5-10 parts of yttrium and 8-20 parts of nanometer alumina particles of which the diameter is 20-30 nm, pretreating the metal raw materials, cutting the pure magnesium ingot, the pure zinc ingot and the magnesium-yttrium alloy into blocks, removing oxides attached on the surface of each metal block, placing the blocks into a resistance furnace to preheat at 180° C. to 200° C., and filtering out the absolute ethyl alcohol after standing, and drying.

Abstract: The present invention relates to a spent fuel dry reprocessing method for directly obtaining a zirconium alloy nuclear fuel, comprising: determining components and a ratio of a molten salt composition used for melting a spent fuel according to a requirement of reactor design on a zirconium alloy fuel and contents of actinium series metals in the spent fuel; melting the spent fuel in the above molten salt composition; and selecting an electrode pair for electrodeposition so that zirconium in the molten salt composition and uranium ions in the spent fuel or uranium and other actinium series metal ions are subjected to co-deposition, thereby obtaining the zirconium alloy nuclear fuel meeting a design requirement. The spent fuel dry reprocessing method provided by the invention is suitable for oxide spent fuel and metal spent fuel, and is simple and controllable in process, low in energy consumption, low in cost and easy to industrialize.

Abstract: Differing from traditional alloys often containing one primary elemental composition, the present invention reforms a conventional superalloy to a high-entropy superalloy by redesigning the elemental compositions of the conventional superalloy based on a mixing entropy formula. Particularly, this high-entropy superalloy shows advantages of light weight and low cost under the premise of containing a low amount of expensive metal composition. The proposed high-entropy superalloy of the present invention comprises a primary elemental composition and at least one principal strengthening elemental composition, wherein the primary elemental composition has a first element content of at least 35 at % and each of the principal strengthening elemental compositions have a second element content of over 5 at %.

Abstract: A metallic coating or alloy is provided. The metallic coating or alloly includes iron, chromium, aluminum, tantalum, and nickel and contains no rhenium. The presence of tantalum and iron and the absence of rhenium are effective to increase a ?/?? transition temperature of the alloy. A component including the metallic coating or alloy is also provided.

Abstract: A gamma radiation source comprises 75Selenium wherein the 75Selenium is provided in the form of compounds, alloys or mixtures with one or more nonmetals which upon irradiation do not produce products capable of sustained emission of radiation which would unacceptably interfere with the gamma radiation of 75Selenium. A further gamma radiation source comprises 75Selenium wherein the 75Selenium is provided in the form of compounds, alloys or mixtures with one or more metals or nonmetals, the neutron irradiation of which does produce products capable of sustained emission of radiation which would acceptably complement the gamma radiation of 75Selenium. Further, the gamma radiation source may have components that are separately irradiated before being combined and the components may be of natural isotopic composition or of isotopically modified composition so that the subsequent radiation peaks may also be adjusted in relative frequency.

Abstract: The present invention relates to a method for the generation of 223Ra of pharmaceutically tolerable purity comprising: i) preparing a generator mixture comprising 227Ac, 227Th and 223Ra in a first aqueous solution comprising a first mineral acid; ii) loading said generator mixture onto a DGA separation medium (e.g. resin); iii) eluting said 223Ra from said DGA separation medium using a second mineral acid in a second aqueous solution to give an eluted 223Ra solution; and iv) stripping the DGA separation medium of said 227Ac and 227Th by flowing a third mineral acid in a third aqueous solution through the DGA separation medium in a reversed direction; The invention further relates to high purity radium-223 formed or formable by such a method as well as pharmaceutical compositions comprising such radium-223 of pharmaceutical purity.

Abstract: Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350° C. to 750° C., and a second additive having a solubility in zirconium over the temperature range extending from 350° C. to 750° C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350° C. to 750° C. and a solubility of the second additive in the first additive over the temperature range extending from 350° C. to 750° C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350° C. to 750° C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.

Abstract: One embodiment of the present invention includes a process for production and recovery of no-carrier-added radioactive tin (NCA radiotin). An antimony target can be irradiated with a beam of accelerated particles forming NCA radiotin, followed by separation of the NCA radiotin from the irradiated target. The target is metallic Sb in a hermetically sealed shell. The shell can be graphite, molybdenum, or stainless steel. The irradiated target can be removed from the shell by chemical or mechanical means, and dissolved in an acidic solution. Sb can be removed from the dissolved irradiated target by extraction. NCA radiotin can be separated from the remaining Sb and other impurities using chromatography on silica gel sorbent. NCA tin-117m can be obtained from this process. NCA tin-117m can be used for labeling organic compounds and biological objects to be applied in medicine for imaging and therapy of various diseases.

Abstract: Molecule for attaching a radioactive parent nuclide to a support, comprising at least one functional group for attaching the radioactive parent nuclide; and a molecular moiety suitable for establishing a nonpolar bond to the support.

Abstract: A method of manufacturing a component. In a preferred embodiment, the method includes enriching an element with an isotope and using the enriched element as a material of the component. A property of the first isotope being the same as a property of a second isotope and is preferably a mechanical, chemical, or electrical property. A second element can also be used as a material of the component, for instance, where the material is an alloy or a composite material. Further, the first isotope can be a lighter isotope of the element. Lightweight components may be manufactured using the method such that mobile platforms (e.g. spacecraft) can be assembled from the component(s). In other exemplary embodiments, the element can be hydrogen, lithium, boron, magnesium, titanium, or iron. Additionally, the component may carry a load. Components including isotopically enriched elements are also provided.

Abstract: A gamma radiation source comprising selenium-75 or a precursor therefore, wherein the selenium is provided in the form of one or more thermally stable compounds, alloys, or mixed metal phases.

Abstract: The invention provides a process for reducing to metallic form oxides of uranium, or metals more noble than uranium, present in spent nuclear fuel comprising a mixture of metal oxides, the process comprising cathodically electrolysing the oxide in the presence of a molten salt electrolyte, the potential of the cathode being controlled so as to favour oxygen ionisation over deposition of the metal from the cations present in the molten salt, and to ensure than reduction of metals other than uranium or metals more noble than uranium does not occur. The invention allows for the reduction of uranium or metals more than uranium present in spent nuclear fuel comprising mixed metal oxides to a metallic form by the use of a single electrochemical process, with oxygen being produced as the only by-product.

Abstract: A perspiration shield takes the form of a multi-layered sheet that is shaped and sized to be placed between adjacent or opposing skin surfaces, such as under the breast, to prevent and absorb perspiration. The multi-layered sheet has an absorbent layer forming one surface of the shield and a silicone gel layer forming another surface of the shield. The silicone gel layer has a soft, tacky texture and readily adheres to the skin but leaves no perceptible residue on the skin when removed. The silicone gel layer closes the pores of the skin with which the layer is in contact, thereby reducing or preventing perspiration from these pores. The absorbent layer absorbs perspiration from the pores of the skin adjacent and opposing the skin surface to which the silicon gel layer is attached and is formed of a material that readily absorbs moisture.

Abstract: An amorphous alloy containing uranium and a member selected from the group of N, P, As, Sb, Bi, S, Se, Te, Po and mixtures thereof; and use thereof for storage medium, light modulator or optical isolator.

Abstract: A cathode is made from tungsten powder using as an impregnant the product rmed from adding about 1 mole of a member selected from the group consisting of zirconium, zirconium dioxide, hafnium, hafnium dioxide, uranium, uranium dioxide, titanium, and titanium dioxide to about 50 to about 100 moles of a compound selected from the group consisting of Ba.sub.3 Al.sub.2 O.sub.6, Ba.sub.3 WO.sub.6, and Ba.sub.4 Al.sub.2 O.sub.7.

Abstract: This invention relates to novel permanent magnet alloy compositions and high energy permanent magnets comprising from about 0.5 to about 27 atomic percent R wherein R is at least one rare earth element including Y and Sc, from about 0.1 to about 53 atomic percent A wherein A is at least one actinide element, and the balance being at least one metal wherein at least about 50 weight percent of the balance is at least one metal selected from the group consisting of Fe, Co, Ni, and Mn. Preferably, R is from about 12 to about 18 atomic percent and R is a rare earth element selected from the group consisting of Sm, Nd, Pr, and Dy. It is also preferred that A is from about 1.5 to about 5.1 atomic percent and A is an actinide element selected from the group consisting of Ac, Th, Pa and U. The balance is preferably at least about 90 weight percent of Fe and/or Co, and further comprises from about 0.1 to about 10 weight percent of Zr and/or Cu.

Abstract: A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).