Patents by Inventor Wolfgang Stoll

Wolfgang Stoll has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).

  • Patent number: 4923639
    Abstract: Method for treating plutonium and/or uranyl nitrate by superheating and concentrating a nitric acid starting solution, characterized by the feature that nitric acid starting solution is concentrated to form a Pu(VI)-and/or U(VI)-containing nitrate melt, is poured into a mold, is solidified by cooling down, and is transported and/or stored as a solidified solid body until further processing.
    Type: Grant
    Filed: January 15, 1982
    Date of Patent: May 8, 1990
    Assignee: Alkem GmbH
    Inventors: Wolfgang Stoll, Christian Ost, Volker Schneider
  • Patent number: 4672213
    Abstract: Container, especially for radioactive substances such as radioactive liquids, with an inner container for receiving these substances and an outer container, in which the inner container and thermal insulation between the inner and outer container are located. The inner container is associated with a cooling tube within the outer container which tube contains a coolant that can be circulated. A heat discharge tube likewise containing the coolant that can be circulated is arranged at the outer container. The cooling tube and the heat discharge tube are in communication with each other via connecting lines at both tube ends.
    Type: Grant
    Filed: November 28, 1984
    Date of Patent: June 9, 1987
    Assignee: Alkem GmbH
    Inventors: Wolfgang Stoll, Ralf Guldner
  • Patent number: 4565672
    Abstract: A method for manufacturing Pu.sub.2 -containing crystals by oxidizing plutonium in a heavily contaminated nitric acid starting solution to Pu.sup.6+, precipitating ammonium plutonyl carbonate containing crystals by reaction with ammonium- and carbonate ions and subsequent separating and calcining of these crystals. The nitric acid solution with the oxidized Pu.sup.6+ as well as carbonate and/or acetate ions and NH.sub.3 are dosed into an aqueous starting solution of ammonium carbonate or ammonium acetate in a concentration such that the mol ratio of carbonate and/or acetate ions to the Pu.sup.6+ -ions in the solution is at least 4:1 and plutonium containing carbonato- or acetato complex compounds which remain dissolved in the receiver solution, are formed, while difficult-to-dissolve metal hydroxide compounds are precipitated. Thereupon NH.sub.3 and carbonate ions are added to precipitate the ammonium plutonyl carbonate containing crystals.
    Type: Grant
    Filed: November 30, 1983
    Date of Patent: January 21, 1986
    Assignee: Alkem GmbH
    Inventors: Volker Schneider, Wolfgang Stoll, Wolf-Gunther Druckenbrodt
  • Patent number: 4528130
    Abstract: Method for dissolving hard-to-dissolve thorium and/or plutonium oxides, especially dioxides such as ThO.sub.2, PuO.sub.2 or (U/Pu)O.sub.2 mixed oxides by heating the oxides in a hermetically sealed vessel in fluoride-free nitric acid. The use of a gas atmosphere containing oxygen in the sealed vessel is advantageous.
    Type: Grant
    Filed: October 13, 1981
    Date of Patent: July 9, 1985
    Assignee: ALKEM GmbH
    Inventors: Friedrich-Wilhelm Ledebrink, Wolfgang Rosenkranz, Wolfgang Stoll
  • Patent number: 4514364
    Abstract: Reprocessing a nuclear reactor fuel rod which contains nuclear fuel in a cladding tube, by removing the cladding tube from the nuclear fuel. The cladding tube is uniformly heated in hermetically sealed condition together with the nuclear fuel contained thereon to permanently expand the diameter of the cladding tube without the formation of cracks in the cladding tube, increasing the distance between the nuclear fuel and the cladding tube. Subsequently the expanded cladding tube is opened at one end. The nuclear fuel is removed from the opened cladding tube and is processed further, separate from the cladding tube.
    Type: Grant
    Filed: July 28, 1983
    Date of Patent: April 30, 1985
    Assignee: Alkem GmbH
    Inventors: Wolfgang Stoll, Karl Ennerst
  • Patent number: 4440067
    Abstract: The hydrostatic actuator in a constant displacement type radial piston pump or engine includes two telescopically arranged component parts separating a high pressure side from a low pressure side for a working medium, and defining a variable pressure space therebetween. The pressure space communicates with the high pressure side via a flow restrictor and with the low pressure side via a pressure limiting valve. The telescopically arranged components parts act as piston-like members and adjust the gaps between the outer end faces of the component parts and their control surfaces of the actuator in response to the pressure in the pressure space.
    Type: Grant
    Filed: December 18, 1979
    Date of Patent: April 3, 1984
    Assignee: G. Dusterloh GmbH
    Inventors: Jurgen Klie, Hans-Wolfgang Stoll
  • Patent number: 4434137
    Abstract: Dissolving hard-to-dissolve nuclear fuels such as ThO.sub.2 and PuO.sub.2 in a nitric acid fission material solution which contains nitric acid and a Pu-fluoride complex to provide free fluorine ions in a small catalytically active amount due to small dissociation of fluoride ions from the Pu-fluoride complex. This permits dissolving hard-to-dissolve nuclear fuels in normal metallic dissolving vessels and also eliminates need for using polytetrafluoroethylene.
    Type: Grant
    Filed: December 3, 1980
    Date of Patent: February 28, 1984
    Assignee: Alkem GmbH
    Inventors: Wolfgang Stoll, Wilhelm Ledebrink
  • Patent number: 4293438
    Abstract: Recovering fission material from solid raw wastes and producing a space-saving product which can be committed to ultimate storage by the following steps:(a) a comminution of the raw wastes to a grain size of about 5 mm(b) dissolution thereof at elevated temperature in an organic solvent until a concentration of about 10 percent by weight is reached(c) separation of insoluble raw waste particles larger than 1 mm.(d) separation of the undissolved fission material content remaining in the polymer solution by means of a centrifuge(e) evaporation and condensation of the solvents for return into the dissolving process according to (b)(f) embedding the waste component from (c) into the remaining plastic melt(g) drawing-off the melt and solidification thereof in storage containers.
    Type: Grant
    Filed: January 30, 1980
    Date of Patent: October 6, 1981
    Assignee: Alkem GmbH
    Inventors: Friedrich-Wilheim Ledebrink, Wolfgang Stoll, Dieter Schafer
  • Patent number: 4235740
    Abstract: Manufacture of uranium/plutonium oxide mixed crystals soluble in nitric acid in which a solution of uranium nitrate and plutonium nitrate are oxidized to cause the plutonium to reach valence VI. The oxidized solution is admixed with ammonium carbonate, oxalate or carbamate and the pH adjusted to 8.1 to 8.5 to precipitate an ammonium uranyl plutonyl carbonate, oxalate or carbamate. The precipitate is calcined to uranium/plutonium oxide.
    Type: Grant
    Filed: March 13, 1979
    Date of Patent: November 25, 1980
    Assignee: Alkem GmbH
    Inventors: Wolf-Gunther Druckenbrodt, Siegfried Baumann, Roland Krause, Wolfgang Stoll