Nukem Limited

Horst Vietzke

Elmar Schlich

Paul Borner

Hans Pirk

Hans Huschka

Gunther Luthardt

Hans-Jorg Isensee

Gerhard Wagner

Paul Arntzen

Herbert Brunner

Alfred Chrubasik

Hans Wingender

Eduard Bregulla

There is proposed for the final storage of radioactive wastes a container made of an uranium alloy which compared to known containers made of uranium is less susceptible to corrosion and does not show any anisotropic thermal expansion at high temperatures. For this purpose, there is alloyed with uranium, which is preferably depleted, 5 to 15 wt. % molybdenum, 2 to 15 wt. % copper, 1 to 5 wt. % zirconium, 0.5 to 5 wt. % chromium, 0.5 to 2 wt. % nickel, 0.5 to 1.5 wt. % niobium, and 0 to 5 wt. % iron with the proviso that the total content of the alloying metals is 10 to 16% and the total of chromium, nickel, and niobium is at least 1.5%.

Container for the final storage of radioactive wastes

For the transportation and long time storage of radioactive waste, especially of spent fuel elements, in suitable geological formations, there are needed multi-layered containers which guarantee a tight sealing even for a long period of time, are corrosion resistant to salt liquors, without being too expensive and too heavy. This is obtained by using for the individual layers of the container different metals or metal alloys which, from the outside inwardly, always are more noble (positive) in the electromotive (electrochemical) series.

Multiple layered transportation and storage container for radioactive

Radioactive, particularly tritium containing, waste must be stored in such manner that the environment is not endangered. This is done by conditioning the waste and embedding it in concrete whereby a central temperature of the product of 90.degree.-95.degree. C. must not be exceeded and therewith a dilution is necessary. These difficulties are overcome by inserting the waste in a metal matrix so that the waste is pressed with a metal powder at room temperature to molded bodies.

Process for embedding radioactive, especially tritium containing waste

Previously known extraction columns for fissionable material (nuclear fuel) and breeder material in the reprocessing of spent fuel elements with pulsation mechanisms working by air impulses, drag along the radioactive aerosols. These difficulties are avoided with the extraction column of the invention in which the column body contains a central tube filled with extraction agent which is connected with a pulsating pump via a multiple part sealing liquid container with the parts joined together according to the principle of communicating tubes.

Extraction column for fissionable material and/or fertile material

There is provided a furnace for incinerating nuclear fission and/or fertile material waste, particularly plutonium and/or uranium containing organic waste by pyrohydrolysis with steam or burning with air oxyen in safe geometry, said furnace comprising in combination a stationary cylindrical outer jacket having a funnel shape at the bottom thereof, a rotatable inner cylinder likewise terminating at the bottom in a funnel shape whose diameter is so regulated that the interval between the outer jacket and the inner cylinder guarantees a safe layer thickness and scrapers which are disposed on the inner surface of the outer jacket and the outer surface of the inner cylinder.

Furnace for incineration of nuclear fission and fertile material waste

Uranium hexafluoride having a high U-235 content is driven out of a transportation container by heating in a correspondingly heated container using a halogenated hydrogen free organic liquid as the heating medium. There is also provided an apparatus for carrying out the process comprising a container having a reflux condenser and an insert for holding the transportation container closed at the bottom by condensate outlet.

Process for expelling uranium hexafluoride having a high U-235 content

There is provided a process for the production of pourable, directly compactable uranium dioxide powder by continuous precipitation of uranium peroxide from a stirred uranyl nitrate solution at a pH of 1 - 2.5 with hydrogen peroxide, calcining of the peroxide at 500.degree.- 800.degree. C. and subsequent reduction at 550.degree.- 750.degree. C. The precipitation solution contains 70 - 150 g/l of uranium and 0.80 g/l of ammonium nitrate and is treated with 15 - 20% aqueous hydrogen peroxide solution in the ratio of U:H.sub.2 O.sub.2 from 1:1.5 to 1:3 and there is led through the solution a mixture of ammonia and air having an air-ammonia volume ratio of 1:0.3 - 0.6. An apparatus for carrying out the process is also described. SU

Growing community of inventors

Maintal, Germany

Horst Vietzke