A process for controlling the dissolution of a metal in an acid bath is described. The metal may comprise aluminum and the acid bath may contain a metal catalyst that causes the metal to dissolve. In order to control the rate of dissolution, the metal can be contacted with a cathodic member. In one embodiment, the process can be completely stopped even without removing the metal from the acid bath. The cathodic member provides anodic protection to the metal. In one embodiment, the cathodic member is made from a nickel-chromium-based alloy.

The invention relates to a method for producing rock wool and cast iron by melting a mixture of materials such as basalt, blast-furnace slag, coke and components necessary for melting, with an admixture containing alumina, said admixture making it possible to adjust the alumina content in order to obtain a rock wool having the following composition (as wt %): Al2O3: 18-22; SiO2: 40-50; CaO: 10-15; MgO: <10; FeO: <2; Na2O: <4; K2O: <2. The method includes the following operations: producing by melting a slag and a cast iron, separating the slag and the cast iron, and performing a fibring operation on the slag followed by a bonding operation in order to obtain the rock wool. According to the invention, at least one spent adsorbent and/or catalyst is used as an admixture, said catalyst containing alumina in Al2O3 form. Said adsorbent and/or catalyst preferably contains at least one metal, and said metal is retrieved in the cast iron.

A process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants. The uranium is therefore available for reuse, storage, or disposal.

On molten iron having a P concentration of 2 to 4 mass % and having a Cr concentration of 0.3 to 1.2 mass %, a dechromization treatment is performed by adjusting a basicity (CaO mass %)/(SiO.sub.2 mass %) of slag to greater than 0.1 and 1 or less and supplying an oxygen source with a molten iron temperature falling within a range of 1250 to 1500° C. to manufacture molten iron having a P concentration of 1.9 to 3.8 mass % and having a Cr concentration of less than 0.2 mass %.

The present invention discloses a method of utilizing refuses in urban and rural areas. The method includes a refuses collection step, a refuse distributing step, a primary magnetic separation step, a primary crushing step, a primary elutriation and floatation step, a uniform cutting step, an acidification and anaerobic treatment step, a selection and separation step, a buffering and adjusting step, an additional anaerobic treatment step and a sludge sedimentation and concentration step. The present invention can make the anaerobic treatment method continuatively dispose the refuses, thereby thoroughly solving the problem that non-anaerobic refuses such as waste plastics, water fiber etc. can not be recycled and completely recycling resources in the refuses.

A method for recovering solder from solder coated scrap pieces includes a step of containing a quantity of solder coated scrap pieces within a centrifuge receptacle of a first centrifuge. The centrifuge receptacle has perforation holes and is rotatably mounted about a first centrifuge axis. A solder collection container surrounds the centrifuge receptacle. The method further includes the steps of heating the solder coated scrap pieces and melting the solder thereon with a heater surrounding the solder collection container and with a drive system, rotating the centrifuge receptacle while the first centrifuge axis is in about a horizontal position at a low speed and tumbling the scrap pieces along a longitudinal length of the centrifuge receptacle, and later rotating the centrifuge receptacle at a high speed for centrifugally extracting molten solder from the centrifuge receptacle, radially outwardly through the perforation holes into the solder collection container.

The invention concerns an apparatus and a method for treating radioactive material (36), in particular for cleaning radioactive contaminated water. The apparatus comprises a process chamber (10) with a combustion zone (12) for generating an oxygen rich gas (34) and an oxidation zone (14), which is arranged to receive the oxygen rich gas (34) from the combustion zone (12). The process chamber (10) further comprises a feed opening (16) for feeding the radioactive material (36) into the oxidation zone (14) and the process chamber (10) is configured to use the oxygen rich gas (34) for oxidizing the radioactive material (36) to obtain oxidized material (38). The apparatus further comprises a separation device (50) operationally connected to an outlet of the process chamber (10) and configured to at least partly separate the oxidized material (38) into a gaseous fluid (56) and a non.sup.− gaseous residue (58). This way a greatly reduced volume of the radioactive material (36) is achieved, enabling safe and efficient handling and/or compact and space-saving disposal of the radioactive material (36).

Described are methods for the recovery of uranium from uranium hexafluoride dissolved directly into ionic liquids.

A carbon offset credit calculation system utilizing waste oil includes a first terminal device inputting information relating to waste oil regarded as a biomass resource; a second terminal device owned by a fuel manufactory and inputting information relating to biofuel, which is purified from waste oil. The fuel manufactory produces the biofuel based on the waste oil. The system includes a third terminal device owned by a site consuming biofuel and inputting information relating to power generation and fuel consumption; and a carbon offset credit calculation server, which calculates a carbon offset amount based on information input by the first terminal device, the second terminal device, and the third terminal device, and calculates a carbon offset credit based on the carbon offset amount. The first terminal device, the second terminal device, the third terminal device, and the carbon offset credit calculation server are connected to one another via the network.

The disclosure relates to a method for sorting a collection of bodies including cemented carbide bodies and non-cemented carbide bodies. A melt having one or more of bismuth, tin and lead and having a density in the range of 7.0-12.0 g/cm.sup.3 is provided. The collection is subjected to a sorting process based on density difference by providing the collection in the melt and allowing the bodies to be sorted into a first group at a top surface of the melt and a second group at a bottom of the melt. The first group includes non-cemented carbide bodies having a density lower than the density of the melt and the second group includes cemented carbide bodies having a density higher than the density of the melt. The present disclosure also relates to a method for recycling of cemented carbides comprising the sorting method and recycling of the second group.