Abstract: Method for removing of organic residues from finely structured surfaces, characterized in that the residues are incinerated by means of ozone.

Abstract: Method for removing of organic residues from finely structured surfaces, in which the residues are incinerated by ozone.

Abstract: Stackable long-term storage container especially for radioactive waste comprises especially convoluted lid and bottom pieces to facilitate stacking. The lid is convoluted providing an annular projection which serves to allow grabbing of the lid and, together therewith, the drum. The floor has a rim which extends axially away from the floor and then is bent over upward toward the drum with drainage openings provided at the bottom edge. A resilient jacket is disposed around the bottom edge and surrounds the rim to prevent direct contact between the drums and scratching during stacking. A fiberglass reinforced plastic insert inside the drum protects the inner wall from damage. The special shape of the drum prevents causes for corrosion under all operating conditions of the drum, especially during very rough handling of the drum during filling, transport and storage.

Abstract: A solid fixation product of harmful, water-containing waste materials and cement, which product is highly resistant to leaching by water and salt solutions. The product has a high content of 20 to 50% of waste materials based on the dry weight of the waste in the product and a water content corresponding to a water-to-cement ratio of 0.2 to 0.45. The method according to the invention which permits producing of such products is characterized in that evaporation of the water-containing waste materials and the mixing with the fixation matrix takes place concurrently at temperatures of 100.degree. to 180.degree. C. The resulting solid fixation product is of relatively small volume and, accordingly, requires only relatively little storage space.

Abstract: A method for forming a hardened product containing a radioactive ion exchanger resin in a condition for permanent, noncontaminating storage, by the steps of:providing, before fixing, a mass of such ion exchanger resin saturated in water, the resin being at least one resin selected from the group consisting of spherical resins and powdered resins;mixing the resin mass, with stirring, with a blast furnace cement having a composition which causes it to exhibit slow initial hardening, high sulfate resistance and low hydration heat and with a quantity of additional water equal in weight to 20% to 40% of the weight of the blast furnace cement; andallowing the resulting mixture to harden at room temperature.

Abstract: A method for solidifying medium radioactive aqueous waste liquids, low radioactive aqueous waste liquids, and aqueous waste liquids containing tritium for final non-contaminating storage. The waste liquids are first mixed with absorbing agents, e.g., clay-like substances, hydraulic binders or mixtures thereof, to form granules or pellets of the same. The granules or pellets are then embedded with a binder which is initially present in a liquid state and later hardens. However, granules or pellets formed from medium radioactivity aqueous waste liquids or waste liquids containing tritium compounds are first clad in a first binder and thereafter embedded for final solidification with a second binder.

Abstract: Method for solidifying high and medium radioactivity and/or actinide containing aqueous waste concentrates or fine-grained solid wastes suspended in water for final noncontaminating storage. The waste concentrates or suspensions are set, by evaporation, to a water content in the range between 40 and 80 percent by weight, and a solid content whose metal ion and/or metal oxide component lies between 10 and 30 percent by weight of the evaporate being formed. The pH of the evaporate is set to between 5 and 10. The resulting evaporate is then pelletized with the aid of a clay-like substance. The pellets are then heat treated, including drying at temperatures between room temperature and about 150.degree. C., then calcining at room temperatures up to about 800.degree. C. and subsequently firing at temperatures between 800.degree. C. and 1400.degree. C. to form practically undissolvable mineral phases. The pellets are then enclosed on all sides in a dense, continuous ceramic or metallic matrix.

Abstract: 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.