Method of decontaminating a metal surface in a nuclear power plant

US11244770B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-11244770-B2
Application numberUS-201816310498-A
CountryUS
Kind codeB2
Filing dateJun 28, 2018
Priority dateJul 6, 2017
Publication dateFeb 8, 2022
Grant dateFeb 8, 2022

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  1. Title

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  2. Abstract

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  3. Assignees and inventors

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  4. Key dates

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  5. First independent claim

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  6. CPC / IPC classifications

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  7. Citations and related patents

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Abstract

Official abstract text for this publication.

A method of decontaminating a metal surface located on a component within a nuclear plant, in particular within the cooling system of a nuclear power plant, which is covered with a metal oxide layer containing radioactive substances, the method including a decontamination step in which a metal oxide layer pretreated in an oxidation step is contacted with an aqueous solution of an organic acid to dissolve the metal oxide layer, forming a decontamination solution containing the organic acid, metal ions and the radioactive substances, and passing the decontamination solution over an ion exchanger to immobilize metal ions and radioactive substances. An oxidant selected from oxygen, air, hydrogen peroxide and ozone is dosed into the decontamination solution to control the dissolution rate of the metal oxide layer. The method is particularly suitable for large-scale system decontamination and ensures high process stability.

First claim

Opening claim text (preview).

The invention claimed is: 1. A method of decontaminating a metal surface, wherein the metal surface is located on a component within a nuclear plant and is covered with a metal oxide layer containing radioactive substances, and wherein the method comprises the following steps: a) an oxidation step in which the metal oxide layer is contacted with an aqueous oxidation solution comprising an oxidant; b) a decontamination step wherein the metal oxide layer treated in the oxidation step is contacted with an aqueous solution of an organic acid to dissolve the metal oxide layer, thereby forming a decontamination solution that contains the organic acid as well as metal ions and the radioactive substances, and wherein the decontamination solution is passed over an ion exchanger to immobilize the metal ions and the radioactive substances; wherein in step b) an oxidant selected from the group consisting of oxygen, air, hydrogen peroxide and ozone is dosed into the decontamination solution; wherein the decontamination solution contains both nickel ions and iron ions and the nickel ions, in the decontamination step, are removed earlier from the decontamination solution than the iron ions; and wherein the decontamination solution is passed over a cation exchanger material, binding the nickel ions on the cation exchanger material, while the iron ions remain in the decontamination solution in the form of an anionic Fe(III) complex. 2. The method according to claim 1 , characterized in that, in the decontamination step, only a plant-internal ion exchanger is used. 3. The method according to claim 1 , characterized in that oxidant dosing is controlled and monitored exclusively with facilities of the nuclear plant. 4. The method according to claim 1 , characterized in that the method is used for large-scale system decontamination. 5. The method according to claim 1 , characterized in that the component is located in a coolant system of a nuclear power plant and comprises one or more of the following components: a pipeline for a primary coolant, a reactor pressure vessel, a coolant pump, a steam generator, a pressure reduction facility and/or at least one auxiliary system connected to the coolant system. 6. The method according to claim 1 , characterized in that, during the decontamination step, a purification rate is in a range of between 0.1 h-1 and 0.7 h-1, the purification rate being defined as a ratio of a flow capacity of the ion exchanger to volume of a system to be decontaminated. 7. The method according to claim 1 , characterized in that dosing of the oxidant into the decontamination solution is controlled such that a dissolution rate of the metal oxide layer of 400 ppm Fe/h is not exceeded. 8. The method according to claim 1 , characterized in that dosing of the oxidant into the decontamination solution is controlled such that a concentration of Fe(II) ions in the decontamination solution of 50 ppm is not exceeded. 9. The method according to claim 1 , characterized in that dosing of the oxidant into the decontamination solution is controlled dependent on available flow capacity of the ion exchanger, system volume and area of the metal surface to be decontaminated. 10. The method according to claim 1 , characterized in that dosing of the oxidant into the decontamination solution is controlled such that a ratio of a dissolution rate of the metal oxide layer to a purification rate is at most 25 ppm Fe, the purification rate being defined as the ratio of a flow capacity (m3/h) of the ion exchanger to a volume (m3) of a system to be decontaminated. 11. The method according to claim 1 , characterized in that hydrogen peroxide is used as an oxidant and dosed into the decontamination solution in an amount of between 0.1 and 1 L per h per 100 m3 of system volume. 12. The method according to claim 1 , characterized in that air, oxygen or ozone is used as an oxidant and that the oxidant is dosed by forced ventilation of a proportion of the decontamination solution. 13. The method according to claim 1 , characterized in that air, oxygen or ozone is directly introduced into the decontamination solution under pressure. 14. The method according to claim 1 , characterized in that the oxidant is continuously dosed into the decontamination solution. 15. The method according to claim 1 , characterized in that the oxidant is dosed into the decontamination solution in a time-delayed manner after a beginning of the decontamination step. 16. The method according to claim 1 , characterized in that dosing of the oxidant into the decontamination solution is controlled by monitoring one or more physical and/or electrochemical parameters of the decontamination solution. 17. The method according to claim 16 , characterized in that a reduction-oxidation potential, a corrosion potential, a conductivity and/or a total oxygen content of the decontamination solution are monitored and used to control the dosing of the oxidant. 18. The method according to claim 17 , characterized in that the reduction-oxidation potential and/or the corrosion potential are set such that the organic acid cannot cause a base metal attack on the metal surface. 19. The method according to claim 17 , characterized in that oxidant dosing is controlled such that a limit value for the corrosion potential and/or the reduction-oxidation potential of the decontamination solution of 0 mV is not undershot. 20. The method according to claim 17 , characterized in that dosing of the oxidant into the decontamination solution begins as soon as the corrosion potential and/or the reduction-oxidation potential of the decontamination solution has dropped to a value in a range from 20 to 180 mV. 21. The method according to claim 1 , characterized in that the decontamination step is followed by a purification step in which the organic acid contained in the decontamination solution is removed and optionally decomposed, with the oxidation step, the decontamination step and the purification step being optionally repeated. 22. The method according to claim 1 , wherein the metal surface is located on a component within a coolant system of a nuclear power plant. 23. The method according to claim 4 , characterized in that the method is used for full system decontamination. 24. The method according to claim 22 , characterized in that, during the decontamination step, a purification rate is in a range of between 0.1 h-1 and 0.7 h-1, the purification rate being defined as a ratio of a flow capacity of the ion exchanger to volume of the coolant system to be decontaminated. 25. The method according to claim 22 , characterized in that air, oxygen or ozone is used as an oxidant and that the oxidant is dosed by forced ventilation of a proportion of the decontamination solution diverted from the coolant system. 26. The method according to claim 15 , characterized in that the dosing of the oxidant begins after the decontamination solution has reached a total iron concentration of at least 20 ppm.

Assignees

Inventors

Classifications

  • Nuclear fission reactors · CPC title

  • G21F9/28Primary

    Treating solids · CPC title

  • G21F9/004Primary

    of metallic surfaces · CPC title

  • Chemical surface treatment, e.g. corrosion (corrosion prevention in presence of water from scale removal or by modification of the properties of the liquid C02F5/00; inhibiting corrosion by adding corrosion inhibitors C23F11/00) · CPC title

  • by absorption; by adsorption; by ion-exchange · CPC title

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What does patent US11244770B2 cover?
A method of decontaminating a metal surface located on a component within a nuclear plant, in particular within the cooling system of a nuclear power plant, which is covered with a metal oxide layer containing radioactive substances, the method including a decontamination step in which a metal oxide layer pretreated in an oxidation step is contacted with an aqueous solution of an organic acid t…
Who is the assignee on this patent?
Framatome Gmbh
What technology area does this patent fall under?
Primary CPC classification G21F9/28. Mapped technology areas include Physics.
When was this patent published?
Publication date Tue Feb 08 2022 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 8 related publications on this page (citations in our corpus or others sharing the same primary CPC).