Abstract:
A method for converting depleted uranium tetrafluoride (UF4) to triuranium octaoxide (U3O8), and producing sulfur tetrafluoride, using a two step process. The first step uses heat and a mixture of the uranium tetrafluoride and an alkaline compound, either an alkaline oxide or an alkaline hydroxide, to produce U3O8 and a water-soluble metal halide. The second step uses heat, sulfur and a halogen to produce sulfur tetrafluoride and triuranium octaoxide.
Abstract translation:使用两步法将贫铀四氟化铀(UF4)转化为三氧化铀(U3O8)并生产四氟化硫的方法。 第一步使用热和四氟化铀与碱性化合物(碱性氧化物或碱性氢氧化物)的混合物来制备U 3 O 8和水溶性金属卤化物。 第二步使用热,硫和卤素来产生四氟化硫和三氧化铀八氧化物。
Abstract:
A method of treating a gas based on fluorine and containing hydrofluoric acid, and which may optionally contain condensable gaseous compounds, especially uranium compounds, and non-condensable gases. The gas is refrigerated to obtain a gaseous component containing fluorine and any non-condensable gases present, and a liquid phase containing liquid HF and condensable compounds in solution and/or suspension. The liquid phase is filtered to recover the compounds in suspension.
Abstract:
A multichamber type fluid bed reaction apparatus has a series of chambers formed by dividing the fluid bed part and the wind box part thereof with particular walls. Each reaction chamber is supplied with a reaction gas whose composition, flow amount and temperature can be selected arbitrarily. A fluid bed, a moving bed or a fixed bed may be used in each divided chamber. Regulation of particle formation, gas-particle reaction and amount of particles transferring between the chambers results in an improvement of efficiency and a simplification of the apparatus.
Abstract:
A pulsed flow process for the reduction of UF.sub.6 where the process may be continuous or batch starting without a seed bed. The initial amplitude and frequency of the pulsed flow is altered as a bed of particle-form material is formed and thereafter the particle-form product of the reaction is removed from the reaction zone.
Abstract:
A process for separately recovering uranium, plutonium and neptunium substantially free of fission products from irradiated nuclear fuel is presented in which the fuel is dissolved in a strong mineral acid forming an aqueous dissolved nuclear fuel solution and treated to separate the uranium, plutonium and neptunium therefrom substantially free of said fission products by the sequential steps of solvent extraction, ion exchange and fluorination. The process has an improvement comprising the addition of a sufficient quantity of an additive of a stable metallic complex to the aqueous dissolved nuclear fuel solution prior to solvent extraction. This achieves improved purity of the separated uranium, plutonium and neptunium.
Abstract:
A method for preparing high purity 233uranium is provided by processing molten salt reactor fuels containing protactinium isotopes in a series of at least two hold-up tanks wherein in the first tank, decay of 232protactinium to 232uranium is permitted to a preselected value and the 232uranium is removed by subsequent fluorination. In the second tank, decay of 233protactinium to 233uranium is permitted to a preselected value and the 233uranium, which is highly depleted in 232uranium, is recovered by subsequent fluorination.