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US4174293A Expired / Lapsed US ⏱️ 0.0 years remaining

Process for disposal of aqueous solutions containing radioactive isotopes

Assignee: United States Department of Energy
•
Filing: 1977-10-12
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Granted: 1979-11-13
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Expires: 1997-10-12
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Abstract

Abstract A process for disposing of radioactive aqueous waste solutions whereby the waste solution is utilized as the water of hydration to hydrate densified powdered portland cement in a leakproof container; said waste solution being dispersed without mechanical inter-mixing in situ in said bulk cement, thereafter the hydrated cement body is impregnated with a mixture of a monomer and polymerization catalyst to form polymer throughout the cement body. The entire process being carried out while maintaining the temperature of the components during the process at a temperature below 99 DEG C. The container containing the solid polymer-impregnated body is thereafter stored at a radioactive waste storage dump such as an underground storage dump.

Inventors

  • 👤 Peter Colombo
  • 👤 Robert M. Neilson, Jr.
  • 👤 Walter W. Becker

Bibliographic Details

Application Number —
Jurisdiction US
Data Source google_patents
Last Synchronized 2026-11-01 20:11
CPC Classifications
G; G21; G21F; G21F9/00; G21F9/04; G21F9/20

Claims Analysis

Total Claims: 8
Claim 1
Independent Claim 169 words
A process for the disposal of aqueous solutions containing radioactive waste material comprising; (a) densifying dry particulate portland cement in a sealable leak-proof container to a bulk density ranging from about 1.3 to about 1.8 grams per cubic centimeter, said cement having a particle size ranging from about 120 mesh to about 400 mesh; (b) dispersing without mechanical agitation from about 15 weight percent to about 30 weight percent of the aqueous solution based upon the weight of the densified cement in-situ within the densified cement; (c) sealing said densified cement containing said aqueous solution off from the atmosphere until the said aqueous solution is hydrated with said cement; (d) impregnating the hydrated cement with a mixture of monomer and a polymerization catalyst and polymerizing the monomer in-situ within the pregnant hydrated cement; (e) storing said pregnant hydrated cement in a suitable storage area; (f) maintaining the temperature of the materials utilized in the process at a temperature below 99° C. throughout steps a thru e of the process.
Claim 2
Dependent Claim 169 words
A process for the disposal of aqueous solutions containing radioactive waste material comprising; (a) densifying dry particulate portland cement in a sealable leak-proof container to a bulk density ranging from about 1.3 to about 1.8 grams per cubic centimeter, said cement having a particle size ranging from about 120 mesh to about 400 mesh; (b) dispersing without mechanical agitation from about 15 weight percent to about 30 weight percent of the aqueous solution based upon the weight of the densified cement in-situ within the densified cement; (c) sealing said densified cement containing said aqueous solution off from the atmosphere until the said aqueous solution is hydrated with said cement; (d) impregnating the hydrated cement with a mixture of monomer and a polymerization catalyst and polymerizing the monomer in-situ within the pregnant hydrated cement; (e) storing said pregnant hydrated cement in a suitable storage area; (f) maintaining the temperature of the materials utilized in the process at a temperature below 99° C. throughout steps a thru e of the process.
Claim 3
Dependent Claim 12 words
The process of claim 1 wherein type III portland cement is used.
Claim 4
Dependent Claim 31 words
The process of claim 2 wherein the temperature of the materials utilized in the process are maintained at a temperature below 90° C. throughout steps a through e of the process.
Claim 5
Dependent Claim 10 words
The process of claim 3 wherein said monomer is styrene.
Claim 6
Dependent Claim 12 words
The process of claim 4 wherein the polymerization catalyst is 2,2 Azobis-2-methylpropionitrile.
Claim 7
Dependent Claim 22 words
The process of claim 5 wherein a safety seal of solid polystyrene is formed on the surface of said pregnant hydrated cement.
Claim 8
Dependent Claim 18 words
The process of claim 6 wherein the leak-proof container is a 55 gallon drum having leak-proof plastic liner.

References Cited (Backward Citations)

GB938211A Cited
DE1199414B Cited
US3012385A Cited

USPTO Annuity & Maintenance Windows

Annuity Stage Window Opens Payment Deadline Surcharge Period Until Estimated Fee Status
3.5 Years (Year 4) 1982-11-12 1983-05-14 1983-11-13 $2000.00 Window Closed / Lapsed
7.5 Years (Year 8) 1986-11-12 1987-05-14 1987-11-13 $3760.00 Window Closed / Lapsed
11.5 Years (Year 12) 1990-11-12 1991-05-14 1991-11-13 $7700.00 Window Closed / Lapsed

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