摘要:
Solid radioactive waste is incorporated in glass, ceramic or basaltic blocks which are conditioned in waste waters or sludges prior to placement in ultimate storage. The conditioning has the dual benefit of reducing the radioactivity of the radioactive waste and of purifying the waste water or of purifying and facilitating the filterability of the sludge. Such purifying is enhanced by concurrent treatment with oxygen or an oxygen-containing gas and/or with a substance which is readily reduced to radicals.
摘要:
Method and apparatus for encapsulating radioactive plastic wastes, particularly radioactively contaminated ion exchange filter material containing water, in bituminous solidification substances, by drying the radioactive waste separate and apart from the bituminous substance, introducing regulated amounts of dry radioactive waste into the bituminous substance and kneading the mixture at a temperature of 120.degree. C. or lower to encapsulate the dry radioactive waste by the mechanical action of the kneading, and pouring the kneaded, encapsulated radioactive plastic waste into a container. Undesired decomposition with discharge of pollutants into the atmosphere are avoided.
摘要:
Admixtures of radioactive material contaminated phosphoric acid ester and polyvinyl chloride from essentially nonvolatile masses which do not flow.
摘要:
A method for processing aqueous radioactive wastes for noncontaminating and safe handling, transport and final storage wherein nitric acid and/or nitrate containing aqueous radioactive waste solutions are continuously denitrated with formic acid, spray-dried and calcinated in a spray dryer having a spray nozzle surrounded by a reaction chamber, the resulting calcinate is mixed with glass former substances, the mixture is melted and the melt is caused to solidify into a glass, glass ceramic or glass ceramic-like block and the waste gases produced during denitration-drying and calcination are conducted through a filter system in order to remove solid particles that have been carried along by the gas. The process steps of denitration, drying and calcination are effected simultaneously and are terminated with the aid of and the intimate energy exchange in the fine distribute droplets superheated steam in the vicinity of the spray nozzle. The resulting waste gases are cleaned within a filter chamber surrounding the reaction chamber with the spray nozzle. An apparatus is provided for practicing the method.
摘要:
A process of preparing substantially solid wastes containing radioactive or toxic substances for safe, non-pollutive handling, transportation and permanent storage, wherein the wastes are mixed with polymerizable mixtures consisting essentially of monovinyl and polyvinyl compounds and polymerization catalysts, and are converted by polymerization into solid blocks.
摘要:
A process of preparing substantially organic waste liquids containing radioactive or toxic substances for safe, non-pollutive handling, transportation and permanent storage, wherein the liquids are mixed with polymerizable mixtures consisting essentially of one or more monomeric monovinyl compounds and one or more polyvinyl compounds and polymerization catalysts, and the resulting mixtures are converted into solid blocks by polymerization at temperatures in the range of from 15.degree. to 150.degree. C.
摘要:
Highly radioactive liquid wastes are permanently stored in a solidification matrix containing the components of a known borosilicate glass together with nucleation agents selected from the group consisting of oxides of Li, K, Mg, Mo and Cr, fluorides of those metals and of Al, and pure noble metals in the elemental form with particles with sizes smaller than 0.1 .mu.m in diameter, and up to 35% by weight of waste fission and corrosion products or waste fission and corrosion products and gadolinium oxide. The product is produced by denitrating and calcining the radioactive waste solution, melting the calcined waste product together with a borosilicate frit containing nucleation agents at a temperature of between 1,050.degree. and 1,200.degree. C, and maintaining it in its melted state for 3 to 5 hours, subsequently cooling the resulting mixture until to a given temperature and maintaining it at this temperature for a given time period to permit nucleation to occur, then elevating the temperature of the mixture with an constant heating rate until to a given higher temperature, maintaining it at this higher temperature for about 24 hours, and finally cooling it with a constant cooling rate to ambient temperature.