Patent US4512921A successfully refreshed from Google Patents.
US4512921A
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Nuclear reactor cooling system decontamination reagent regeneration
Assignee: United States Department of Energy
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Filing: 1982-09-20
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Granted: 1985-04-23
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Expires: 2002-09-20
Abstract
Abstract An improved method for decontaminating the coolant system of water-cooled nuclear power reactors and for regenerating the decontamination solution. A small amount of one or more weak-acid organic complexing agents is added to the reactor coolant, and the pH is adjusted to form a decontamination solution which is circulated throughout the coolant system to dissolve metal oxides from the interior surfaces and complex the resulting metal ions and radionuclide ions. The coolant containing the complexed metal ions and radionuclide ions is passed through a strong-base anion exchange resin bed which has been presaturated with a solution containing the complexing agents in the same ratio and having the same pH as the decontamination solution. As the decontamination solution passes through the resin bed, metal-complexed anions are exchanged for the metal-ion-free anions on the bed, while metal-ion-free anions in the solution pass through the bed, thus removing the metal ions and regenerating the decontamination solution.
Inventors
- 👤 Larry D. Anstine
- 👤 Dean B. James
- 👤 Edward A. Melaika
- 👤 John P. Peterson, Jr.
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-01 17:19
CPC Classifications
G; G21; G21F; G21F9/00; G21F9/001; G21F9/002; G21F9/004
Claims Analysis
Total Claims: 10
Claim 1
Independent Claim
196 words
A method of removing corrosion products from the coolant system of a water-cooled nuclear reactor comprising the steps of: (a) adding at least one soluble weak-acid organic complexing agent selected from the group consisting of oxalic acid, citric acid, nitrilotriacetic acid and hydroxyethylethylenediaminetriacetic acid to the coolant to form a decontamination solution; (b) adjusting the pH of the decontamination solution to from 2.5 to 4.0; (c) circulating and decontamination solution at a temperature of from 60° to 100° C. throughout the coolant system to dissolve the corrosion products to form a complexed ion solution of Fe +2 , Fe +3 , 60 Co +2 , and other metal ion complexes; and (d) removing the Fe +2 , Fe +3 and 60 Co +2 complexes from the complexed ion solution and regenerating the decontamination solution by passing the complexed ion solution through an anion exchange resin, said anion exchange resin having been presaturated with the anions of the weak-acid organic complexing agent of the decontamination solution such that the concentration of the agents on the resin is substantially the same concentration of the agents in the decontamination solution and having the same pH of the decontamination solution.
Claim 2
Independent Claim
196 words
A method of removing corrosion products from the coolant system of a water-cooled nuclear reactor comprising the steps of: (a) adding at least one soluble weak-acid organic complexing agent selected from the group consisting of oxalic acid, citric acid, nitrilotriacetic acid and hydroxyethylethylenediaminetriacetic acid to the coolant to form a decontamination solution; (b) adjusting the pH of the decontamination solution to from 2.5 to 4.0; (c) circulating and decontamination solution at a temperature of from 60° to 100° C. throughout the coolant system to dissolve the corrosion products to form a complexed ion solution of Fe +2 , Fe +3 , 60 Co +2 , and other metal ion complexes; and (d) removing the Fe +2 , Fe +3 and 60 Co +2 complexes from the complexed ion solution and regenerating the decontamination solution by passing the complexed ion solution through an anion exchange resin, said anion exchange resin having been presaturated with the anions of the weak-acid organic complexing agent of the decontamination solution such that the concentration of the agents on the resin is substantially the same concentration of the agents in the decontamination solution and having the same pH of the decontamination solution.
Claim 3
Dependent Claim
17 words
The method of claim 1 wherein the decontamination solution contains from 0.2 to 4.0 ppm dissolved oxygen.
Claim 4
Dependent Claim
27 words
The method of claim 2 wherein the weak-acid organic complexing agents comprise from 0.005 to 0.02M in oxalic acid and from 0.002 to 0.01M in citric acid.
Claim 5
Dependent Claim
14 words
The method of claim 1 wherein the nuclear reactor is a boiling water reactor.
Claim 6
Dependent Claim
19 words
The method of claim 1 further comprising the step of recirculating the regenerated decontamination solution through the coolant system.
Claim 7
Dependent Claim
222 words
In the method of removing corrosion products from the coolant system of a water-cooled nuclear reactor by: (a) adding at least one soluble weak-acid organic complexing agent selected from the group consisting of oxalic acid, citric acid, nitrilotriacetic acid and hydroxyethylethylenediaminetriacetic acid to the coolant to form a decontamination solution; (b) adjusting the pH of the decontamination solution to from 2.5 to 4.0; (c) circulating the decontamination solution at a temperature of from 60° to 100° C. throughout the coolant system to dissolve the corrosion products to form a complexed ion solution of Fe +2 , Fe +3 , 60 Co +2 , and other metal ion complexes; and (d) passing the complexed ion solution through a cation exchange resin; wherein the improvement comprises: replacing the cation exchange resin with a pretreated anion exchange resin, said pretreated anion exchange resin having been presaturated with the anions of the weak-acid organic complexing agent of the decontamination solution such that the concentration of the agents in the resin is substantially the same concentration of the agents in the decontamination solution and having the same pH of the decontamination solution, whereby passing the complexed ion solution through the pretreated anion exchange resin removes the Fe +2 , Fe +3 , and 60 Co +2 ions from the complexed ion solution and regenerates the decontamination solution.
Claim 8
Dependent Claim
222 words
In the method of removing corrosion products from the coolant system of a water-cooled nuclear reactor by: (a) adding at least one soluble weak-acid organic complexing agent selected from the group consisting of oxalic acid, citric acid, nitrilotriacetic acid and hydroxyethylethylenediaminetriacetic acid to the coolant to form a decontamination solution; (b) adjusting the pH of the decontamination solution to from 2.5 to 4.0; (c) circulating the decontamination solution at a temperature of from 60° to 100° C. throughout the coolant system to dissolve the corrosion products to form a complexed ion solution of Fe +2 , Fe +3 , 60 Co +2 , and other metal ion complexes; and (d) passing the complexed ion solution through a cation exchange resin; wherein the improvement comprises: replacing the cation exchange resin with a pretreated anion exchange resin, said pretreated anion exchange resin having been presaturated with the anions of the weak-acid organic complexing agent of the decontamination solution such that the concentration of the agents in the resin is substantially the same concentration of the agents in the decontamination solution and having the same pH of the decontamination solution, whereby passing the complexed ion solution through the pretreated anion exchange resin removes the Fe +2 , Fe +3 , and 60 Co +2 ions from the complexed ion solution and regenerates the decontamination solution.
Claim 9
Dependent Claim
19 words
The method of claim 6 further comprising the step of recirculating the regenerated decontamination solution through the coolant system.
Claim 10
Dependent Claim
46 words
The method of claim 5 or 7 further comprising the step of purifying the coolant system to remove the organic complexing agents and any metal ion complexes remaining in the system by passing the regenerated decontamination solution through a mixed-bed of anion and cation exchange resins.
References Cited (Backward Citations)
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1988-04-22 | 1988-10-22 | 1989-04-23 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1992-04-22 | 1992-10-22 | 1993-04-23 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1996-04-22 | 1996-10-22 | 1997-04-23 | $7700.00 | Window Closed / Lapsed |