Abstract:
The present invention is directed to a process for recycling of a sodium salt by decomposition of a sodium nitride liquid waste. The process comprises: a neutralization step in which a nitric acid liquid waste or an off-gas having nitric acid dissolved therein which is produced through a wet reprocessing process comprising a dissolution step for dissolving a spent nuclear fuel in nitric acid is neutralized by adding or contacting the nitrate liquid waste or the off-gas to or with at least one sodium salt selected from sodium hydroxide, sodium hydrogencarbonate and sodium carbonate, thereby yielding a sodium nitrate liquid waste; a sodium nitrate-decomposition step in which the sodium nitrate liquid waste is reductively decomposed with a reducing agent, thereby decomposing sodium nitrate into a nitrogen gas and the sodium salt; and a recycle step for recycling the sodium salt into the neutralization step or wet reprocessing process. The sodium nitrate liquid waste obtained in the neutralization step may be concentrated by evaporation to give a concentrated sodium nitrate liquid waste, and the condensed sodium nitrate liquid waste may be reductively decomposed in the sodium nitrate-decomposition step.
Abstract:
The product of a molten alkali metal metalate phase separation can be processed into a purified metal from a metal source. Metal sources include native ores, recycled metal, metal alloys, impure metal stock, recycle materials, etc. The method uses a molten alkali metal metalate as a process medium or solvent in purifying or extracting high value metal or metal oxides from metal sources. Vitrification methods using the silicate glass separation phase can be prepared as is or can be prepared with a particulate phase distributed throughout the silica glass phase and encapsulated and fixed within the continuous glass phase. Tungsten metal can be obtained from an alkali metal tungstate. A typically finely divided tungsten metal powder can be obtained from a variety of tungsten sources including recycled tungsten scrap, tungsten carbide scrap, low grade tungsten ore typically comprising tungsten oxide or other form of tungsten in a variety of oxidation states.
Abstract:
A generator that allows for a non-fission based method of producing and recovering 99mTc from neutron-irradiated molybdenum. This generator system is based on the isolation of 99mTc, as the decay product from a source of 99Mo labelled molybdenum carbonyl Mo(CO)6 through a distillation process. The 99mTc obtained from this distillation is produced with high efficiency and purity in a solvent-free form, which can then be dissolved in water or other solvents to produce a solution at the required specific activity and concentration, as reasonably determined by the operator.
Abstract:
A method of stabilizing nuclear material is disclosed. Oxides or halides of actinides and/or transuranics (TRUs) and/or hydrocarbons and/or acids contaminated with actinides and/or TRUs are treated by adjusting the pH of the nuclear material to not less than about 5 and adding sufficient MgO to convert fluorides present to MgF2; alumina is added in an amount sufficient to absorb substantially all hydrocarbon liquid present, after which a binder including MgO and KH2PO4 is added to the treated nuclear material to form a slurry. Additional MgO may be added. A crystalline radioactive material is also disclosed having a binder of the reaction product of calcined MgO and KH2PO4 and a radioactive material of the oxides and/or halides of actinides and/or transuranics (TRUs). Acids contaminated with actinides and/or TRUs, and/or actinides and/or TRUs with or without oils and/or greases may be encapsulated and stabilized by the binder.
Abstract translation:公开了一种稳定核材料的方法。 通过将核材料的pH调节至不小于约5并加入足够的MgO以转化氟化物来处理锕系元素和/或trans烷(TRU)和/或被锕系元素和/或TRU污染的烃和/或酸的氧化物或卤化物 存在于MgF 2上; 以足以吸收基本上所有存在的所有烃液体的量添加氧化铝,之后将包含MgO和KH 2 PO 4的粘合剂加入到经处理的核材料中以形成 泥浆。 可以加入另外的MgO。 还公开了一种结晶放射性材料,其具有煅烧的MgO和KH 2 PO 4的反应产物的粘合剂和锕系元素的氧化物和/或卤化物的放射性物质,以及 /或超ur(TRU)。 用锕系元素和/或TRU和/或锕系元素和/或具有或不含油和/或润滑脂的锕系元素和/或TRU污染的酸可以被粘合剂包封并稳定。
Abstract:
A positive electrode active material powder for a non-aqueous electrolyte secondary battery, wherein an amount of a liquid reagent absorbed by the powder is 20 to 40 ml per 100 g of the powder when the liquid reagent is dibutyl phthalate, and the amount is 20 to 50 ml per 100 g of the powder when the liquid reagent is N-methyl-2-pyrrolidone or water, the absorption amount is a value measured using a device according to test method A or B regarding DBP absorption based on JIS K6217 (1997), and the measured value is an amount of the liquid reagent added until the viscosity of a mixture of the powder and the liquid reagent reaches a level corresponding to 70% of a maximum torque which is recorded when a change in the viscosity of a mixture of the powder and the liquid reagent is measured by a torque detecting device.
Abstract:
A system for cooling and recuperative heating of a slurry in a metallurgical process which includes heat exchangers, pumps and autoclaves is described herein. The heat exchangers use a non-scaling common liquid heat transfer medium. Preferably, the heat exchangers are tube-in-tube heat exchangers with 3 to 7 slurry tubes in each heat exchanger. An advantage of this system is that it does not use flash tanks. To minimize abrasive wear on impinged surfaces, the velocity of the slurry is not more than 5 meters per second. The slurry comprises a solids concentration of 25% to 50%. Preferably, the pumps in the system are float-type pumps in which the driven liquid from the discharge pumps is also used as the drive liquid for the feed pumps.
Abstract:
A composition for growing a laser crystal is represented by the formula of Li �R.sub.n .alpha..sub.1-n! �(Ga.sub.p In.sub.q) .beta..sub.1-p-q ! F.sub.6+n where n is within a range from 10.sup.-5 to 0.1, each of p and q is within a range from 0 to 0.6, a total of p and q is within a range from 0.001 to 0.6, .alpha. is at least one member selected from the group consisting of Ca, Sr, Ba and Na, .beta. is at least one member selected from the group consisting of Al, Cr, Ni, Co and Fe, and R is a rare-earth element. The composition enables the distribution coefficient of rare-earth element to get closer to 1 and thus enables the laser crystal to have a high and uniform concentration of rare-earth element and to have a large size.
Abstract:
The invention relates to a method of preparing a radiodiagnostic comprising a gaseous radionuclide formed by radioactive decay of a parent nuclide, by eluting with a suitable eluent the radioactive daughter nuclide from the parent nuclide provided ionically on a carrier, by using as a carrier for the parent nuclide ions a membrane, in particular an ion exchange membrane, past which the eluent is made to flow.The invention further relates to a radionuclide generator suitable for using said method.