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US4460500A Expired / Lapsed US ⏱️ 0.0 years remaining

Method for final treatment of radioactive organic material

Assignee: Studsvik Energiteknik AB
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Filing: 1982-03-16
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Granted: 1984-07-17
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Expires: 2002-03-16
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Abstract

Abstract Radioactive waste, such as expended radioactive ion exchanger mass, can be transformed in a continuous process to a stable state for final storage in the following manner. The waste is mixed with an aqueous solution of a chemical agent which liberates radioactive substances from the waste, and with an inorganic sorbent for the thus liberated radioactive substances. The mixture is now dried and calcinated during the supply of air or oxygen so that the organic material is combusted. Subsequently the calcined material is placed in a refractory storage container, which is now heated with its contents to a temperature at which said material sinters or fuses to a stable product.

Inventors

  • 👤 Ake Hultgren

Bibliographic Details

Application Number —
Jurisdiction US
Data Source google_patents
Last Synchronized 2026-11-06 15:33
CPC Classifications
G; G21; G21F; G21F9/00; G21F9/28; G21F9/30; G21F9/32

Claims Analysis

Total Claims: 11
Claim 1
Independent Claim 112 words
A method for final treatment of a spent radioactive organic ion exchanger mass, for transforming the material to stable form for terminal storage, characterized in that the material is mixed with an aqueous solution of a chemical agent which liberates radioactive substances bound in the material, as well as with an inorganic sorbent for the thus liberated radioactive substances, the mixture being subsequently dried and calcined while air or oxygen is supplied, so that the organic matter is combusted, the calcinated material subsequently being placed in a refractory storage vessel which is then heated together with its contents to a temperature at which the material sinters or fuses to a stable product.
Claim 2
Independent Claim 112 words
A method for final treatment of a spent radioactive organic ion exchanger mass, for transforming the material to stable form for terminal storage, characterized in that the material is mixed with an aqueous solution of a chemical agent which liberates radioactive substances bound in the material, as well as with an inorganic sorbent for the thus liberated radioactive substances, the mixture being subsequently dried and calcined while air or oxygen is supplied, so that the organic matter is combusted, the calcinated material subsequently being placed in a refractory storage vessel which is then heated together with its contents to a temperature at which the material sinters or fuses to a stable product.
Claim 3
Dependent Claim 63 words
Method as claimed in claim 1, wherein said chemical agent which liberates radioactive substances bound in the material is a complex-forming agent selected from the group consisting of phosphoric acid, citric acid, tartaric acid, oxalic acid, a salt of phosphoric acid, a salt of citric acid, a salt of tartaric acid, a salt of oxalic acid, and mixtures of any of the foregoing.
Claim 4
Dependent Claim 51 words
Method as claimed in claim 1, wherein said inorganic sorbent is selected from the group consisting of a titanate, titanium hydroxide, a zirconate, zirconium hydroxide, zirconium phosphate, an aluminate, aluminum hydroxide, aluminum phosphate, an alumino silicate, a natural zeolite, a synthetic zeolite, calcium phosphate, and mixtures of any of the foregoing.
Claim 5
Dependent Claim 17 words
Method as claimed in claim 1, in which mixing takes place at a temperature of 20°-70° C.
Claim 6
Dependent Claim 27 words
Method as claimed in claim 1, in which the temperature during calcination is increased from 300° C. to a final temperature of between 500° and 900° C.
Claim 7
Dependent Claim 25 words
Method as claimed in claim 1, in which the flue gas from the calcination-combustion step are refluxed to the drying step for cleaning the gas.
Claim 8
Dependent Claim 28 words
Method as claimed in claim 1, in which the material after calcination-combustion is sintered or fused, in a final storage container, at 1000°-1300° C. to a stable product.
Claim 9
Dependent Claim 17 words
Method as claimed in claim 1 wherein said chemical agent which literates radioactive substances comprises sodium tartrate.
Claim 10
Dependent Claim 12 words
Method as claimed in claim 1 wherein said inorganic sorbent comprises bentonite.
Claim 11
Dependent Claim 15 words
Method as claimed in claim 1 wherein said inorganic sorbent comprises sodium titanate and bentonite.

References Cited (Backward Citations)

US3375202A Cited
US4118317A Cited
US4053432A Cited
US4122048A Cited
JPS54157000A Cited

USPTO Annuity & Maintenance Windows

Annuity Stage Window Opens Payment Deadline Surcharge Period Until Estimated Fee Status
3.5 Years (Year 4) 1987-07-17 1988-01-16 1988-07-17 $2000.00 Window Closed / Lapsed
7.5 Years (Year 8) 1991-07-17 1992-01-16 1992-07-17 $3760.00 Window Closed / Lapsed
11.5 Years (Year 12) 1995-07-17 1996-01-16 1996-07-17 $7700.00 Window Closed / Lapsed

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