CN100577893C - Electrolytic decontaminating method for removing radioactive contaminant from metal surface - Google Patents
Electrolytic decontaminating method for removing radioactive contaminant from metal surface Download PDFInfo
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- CN100577893C CN100577893C CN200510135004A CN200510135004A CN100577893C CN 100577893 C CN100577893 C CN 100577893C CN 200510135004 A CN200510135004 A CN 200510135004A CN 200510135004 A CN200510135004 A CN 200510135004A CN 100577893 C CN100577893 C CN 100577893C
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Abstract
The electrolytic decontaminating method for eliminating radioactive contaminant from metal surface includes connecting the decontaminated part to the anode of the power source, connecting decontaminating part to the cathode and feeding electrolyte into the electrolytic decontaminator for electrolytic decontaminating. The electrolyte consists of HNO3 in 3-10 wt%, NaNO3 in 5-20 wt% and water for the rest. The electrolytic current density is 0.1- 0.6A/cm2, and the electrolytic temperature is 20-50 deg.c. The electrolytic decontaminating method may be used for eliminating radioactive contaminant from metal parts of exservice nuclear installation, so that the metal waste may be degraded and reused.
Description
Technical field
The present invention relates to the method for radiocontamination material surface decontamination, relate in particular to the alpha-contamination electrolytic decontaminating method in a kind of removal metallic surface.
Background technology
External electrolytic decontaminating technology once was widely used in radioactive decontamination in early days.In the electrolytic decontaminating process, efficient, can be applied to the nuclear installation decontamination to the electrolytic decontaminating technology for the electrolytic solution that nuclear installation is accepted and have important practical significance.Along with the development of nuclear industry and perfect, most electrolytic solution is owing to following reason can not be used for electrolytic decontaminating to the radiocontamination material: (1) prescription contain with the inconsistent chemical ingredients of nuclear installation waste liquid receiving processing system (as S, P, halogen, organism etc.), liquid waste disposal difficulty after the decontamination; (2) rate of metal corrosion during decontamination is very low, and the decontamination time is long, can not realize decontamination rapidly and efficiently, can't embody the advantage of electrolytic decontaminating; (3) temperature requirement is too high during decontamination, needs to be equipped with heating unit, makes eradicator complicated; (4) often contain high concentrated acid in the prescription, strict to the selection of eradicator material, decontamination cost height; (5) the decontamination waste liquid does not have self-purification function, and the electrolytic solution life-span is not long.
Summary of the invention
The object of the present invention is to provide a kind of can making to have nuclear installation acceptance and the strong alpha-contamination electrolytic decontaminating method in removal metallic surface of soil removability now.
The present invention removes the alpha-contamination electrolytic decontaminating method in metallic surface, to treat that the decontamination parts connect power anode, the decontamination parts connect power cathode, carry out electrolytic decontaminating behind the adding electrolytic solution in eradicator, and the electrolyte prescription that is adopted is that mass percent is 3%～10% HNO
3, mass percent is 5%～20% NaNO
3, all the other are water.
The alpha-contamination electrolytic decontaminating method in aforesaid removal metallic surface, preferred electrolyte prescription is that mass percent is 4%～8% HNO
3, mass percent is 8%～13% NaNO
3, all the other are water.
The alpha-contamination electrolytic decontaminating method in aforesaid removal metallic surface, most preferably electrolyte prescription is that mass percent is 5% HNO
3, mass percent is 10% NaNO
3, all the other are water.
The alpha-contamination electrolytic decontaminating method in aforesaid removal metallic surface, current density is 0.1～0.6A/cm in the electrolytic process
2, electrolysis temperature is 20～50 ℃.
The present invention removes the alpha-contamination electrolytic decontaminating method in metallic surface, can be widely used in nuclear installation metallic surface radioactivity electrolytic decontaminating, the a large amount of metal wastes that produce when making the elimination of nuclear facilities are demoted or recirculation, utilize again, in addition, because this method adopts nitric acid system electrolytic solution to also have following advantage: (1) electrolyte prescription composition is compatible with existing nuclear installation waste liquid receiving system, need not special liquid waste disposal facility; (2) rate of metal corrosion is up to 3 μ m/min during electrolysis, and this is that stain remover all in the nuclear installation decontamination both at home and abroad at present is all incomparable, can be used for the difficult point that other stain remover can't accomplish, the decontamination of focus, realizes fast, high-effective cleansing; (3) can be interrupted in the electrolytic decontaminating process and produce precipitation, the radioactivity in the electrolytic solution is with the precipitation enrichment, thereby reaches the effect of electrolytic solution self-purification, realizes regeneration and prolonged work-ing life of electrolytic solution, also can reduce the generation of secondary refuse, realizes waste minimization; (4) decontamination at room temperature, use temperature a wider range, not influenced by ambient temperature, need not heat during decontamination, thereby simplify eradicator, be convenient to the decontamination operation.
Embodiment
Decontamination method:
Treat that the decontamination parts connect power anode, the decontamination parts connect power cathode, make electrolytic solution be full of the anode and cathode space, and electrolyte prescription is that mass percent is 3%～10% HNO
3, mass percent is 5%～20% NaNO
3, all the other are deionized water.In the electrolytic decontaminating process, current density is 0.1～0.6A/cm
2, electrolysis temperature is 20～50 ℃.By the electrolytic dissolution on anode metal surface, make attached to the dissolving of the radioactive pollutant of metallic surface to enter in the electrolytic solution with the metallic surface thin layer, remove alpha-contamination purpose thereby reach.Eradicator can be general slot type electrolytic decontaminating device, also can be formula electrolytic decontaminating device on the spot.
The liquid waste disposal mode:
Electrolytic solution decontamination waste liquid is compatible with existing nuclear installation waste liquid receiving system, need not special liquid waste disposal facility, enters the nuclear installation liquid waste treatment system after can neutralizing or directly enters the nuclear installation liquid waste treatment system.
Embodiment 1
Certain contaminated samples alpha surface pollution is 2.07 * 10
5Cpm, the β surface contamination is 1.58 * 10
4Cpm, the gamma contamination dosage rate is 1.67 * 10
3Cpm.The eradicator that adopts can be general slot type electrolytic decontaminating device, also can be formula electrolytic decontaminating device on the spot.
Contaminated samples is connect positive source as anode, and negative electrode connects power cathode, and electrolytic solution is full of between the anode and cathode, and electrolyte prescription is that mass percent is 5% HNO
3, mass percent is 10% NaNO
3, all the other are water.Electrolysis temperature is a room temperature, and current density is 0.6A/cm
2, behind the electrolysis 15min, the α of contaminated samples, β surface contamination observed value are all near background, and decontamination factor is respectively α: 2.59 * 10
5, β: 1.32 * 10
4, γ: 213.
Embodiment 2
Certain contaminated samples alpha surface pollution is 1.61 * 10
4Cpm, the β surface contamination is 1.54 * 10
4Cpm, the gamma contamination dosage rate is 29cpm.Eradicator can be general slot type electrolytic decontaminating device, also can be formula electrolytic decontaminating device on the spot.
Contaminated samples is connect positive source as anode, and negative electrode connects power cathode, and electrolyte prescription is that mass percent is 4% HNO
3, mass percent is 5% NaNO
3, all the other are water.20 ℃ of electrolysis temperatures, current density are 0.3A/cm
2, behind the electrolysis 20min, the α of contaminated samples, β surface contamination observed value and gamma contamination dosage rate are background values.
Embodiment 3
Certain contaminated samples alpha surface pollution is 2.86 * 10
5Cpm, the β surface contamination is 1.11 * 10
4Cpm, the gamma contamination dosage rate is 413cpm.The eradicator that adopts can be general slot type electrolytic decontaminating device, also can be formula electrolytic decontaminating device on the spot.
Contaminated samples is connect positive source as anode, and negative electrode connects power cathode, and using electrolyte prescription is 4% HNO as mass percent
3, mass percent is 10% NaNO
3, all the other are water, and electrolytic solution is full of between the anode and cathode, and electrolysis temperature is 30 ℃, and current density is 0.6A/cm
2, behind the electrolysis 20min, the alpha surface pollution observed value of contaminated samples is near background, and the gamma contamination dosage rate is a background values, and decontamination factor is respectively α: 1.22 * 10
4, β: 455.
Embodiment 4
Certain contaminated samples alpha surface pollution is 1.05 * 10
4Cpm, the β surface contamination is 1.25 * 10
6Cpm, the gamma contamination dosage rate is 1.81 * 10
4Cpm.The eradicator that adopts can be general slot type electrolytic decontaminating device, also can be formula electrolytic decontaminating device on the spot.
Contaminated samples is connect positive source as anode, and negative electrode connects power cathode, and using electrolyte prescription is 10% HNO as mass percent
3, mass percent is 15% NaNO
3, all the other are water, and 1 is full of electrolytic solution between the anode and cathode, and electrolysis temperature is 40 ℃, and current density is 0.6A/cm
2, behind the electrolysis 30min, the α of contaminated samples, β surface contamination observed value be all near background,, the gamma contamination dosage rate is a background values, decontamination factor is respectively α: 5.02 * 10
3, β: 6.46 * 10
4
Claims (3)
1. remove the alpha-contamination electrolytic decontaminating method in metallic surface for one kind, to treat that the decontamination parts connect power anode, the decontamination parts connect power cathode, carry out electrolytic decontaminating behind the adding electrolytic solution in eradicator, and it is characterized in that: the electrolyte prescription that is adopted is that mass percent is 4%～8% HNO
3, matter
Per-cent is 8%～13% NaNO
3, all the other are water.
2. the alpha-contamination electrolytic decontaminating method in removal according to claim 1 metallic surface is characterized in that: electrolyte prescription is that mass percent is 5% HNO
3, mass percent is 10% NaNO
3, all the other are water.
3. the alpha-contamination electrolytic decontaminating method in removal according to claim 1 and 2 metallic surface is characterized in that: in the electrolytic process, current density is 0.1～0.6A/cm
2, electrolysis temperature is 20～50 ℃.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200510135004A CN100577893C (en) | 2005-12-23 | 2005-12-23 | Electrolytic decontaminating method for removing radioactive contaminant from metal surface |
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|---|---|---|---|
| CN200510135004A CN100577893C (en) | 2005-12-23 | 2005-12-23 | Electrolytic decontaminating method for removing radioactive contaminant from metal surface |
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|---|---|
| CN1986904A CN1986904A (en) | 2007-06-27 |
| CN100577893C true CN100577893C (en) | 2010-01-06 |
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Families Citing this family (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102664053A (en) * | 2012-04-26 | 2012-09-12 | 广东白云国际科学研究院有限公司 | Electrolyte for radioactive contamination electrochemical cleaning |
| CN109295493B (en) * | 2018-10-24 | 2020-05-26 | 中国核动力研究设计院 | Electrochemical in-situ decontamination method for radioactive pollutants on metal surface |
| CN110318091B (en) * | 2019-07-03 | 2021-06-22 | 中广核核电运营有限公司 | Decontamination composition, preparation method thereof and decontamination method of piece to be decontaminated |
| CN110257890A (en) * | 2019-07-03 | 2019-09-20 | 岭东核电有限公司 | Remove foul electrolyte and decontamination method |
| CN110373707B (en) * | 2019-07-03 | 2021-06-22 | 岭东核电有限公司 | Decontamination method and application thereof |
| CN110230088B (en) * | 2019-07-03 | 2020-11-24 | 岭东核电有限公司 | Stain removal composition and stain removal method |
| CN110257891A (en) * | 2019-07-03 | 2019-09-20 | 岭东核电有限公司 | Remove foul electrolyte and decontamination method |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3496017A (en) * | 1966-04-28 | 1970-02-17 | Atomic Energy Commission | Method and composition for decontamination of stainless steel surfaces |
| US4193853A (en) * | 1979-05-15 | 1980-03-18 | The United States Of America As Represented By The United States Department Of Energy | Decontaminating metal surfaces |
| US4318786A (en) * | 1980-03-10 | 1982-03-09 | Westinghouse Electric Corp. | Electrolytic decontamination |
| US4481090A (en) * | 1984-01-23 | 1984-11-06 | The United States Of America As Represented By The United States Department Of Energy | Decontaminating metal surfaces |
| US4661220A (en) * | 1984-07-04 | 1987-04-28 | Ab Asea-Atom | Method for local cleaning of surfaces on a nuclear reactor which are coated with oxides or other corrosion products, in connection with inspection |
| US4704235A (en) * | 1984-03-09 | 1987-11-03 | Studsvik Energiteknik Ab | Decontamination of pressurized water reactors |
| US4836900A (en) * | 1987-01-05 | 1989-06-06 | Commissariat A L'energie Atomique | Process for the decontamination of the surface of a metal port contaminated by tritium and apparatus usable for this process |
-
2005
- 2005-12-23 CN CN200510135004A patent/CN100577893C/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3496017A (en) * | 1966-04-28 | 1970-02-17 | Atomic Energy Commission | Method and composition for decontamination of stainless steel surfaces |
| US4193853A (en) * | 1979-05-15 | 1980-03-18 | The United States Of America As Represented By The United States Department Of Energy | Decontaminating metal surfaces |
| US4318786A (en) * | 1980-03-10 | 1982-03-09 | Westinghouse Electric Corp. | Electrolytic decontamination |
| US4481090A (en) * | 1984-01-23 | 1984-11-06 | The United States Of America As Represented By The United States Department Of Energy | Decontaminating metal surfaces |
| US4704235A (en) * | 1984-03-09 | 1987-11-03 | Studsvik Energiteknik Ab | Decontamination of pressurized water reactors |
| US4661220A (en) * | 1984-07-04 | 1987-04-28 | Ab Asea-Atom | Method for local cleaning of surfaces on a nuclear reactor which are coated with oxides or other corrosion products, in connection with inspection |
| US4836900A (en) * | 1987-01-05 | 1989-06-06 | Commissariat A L'energie Atomique | Process for the decontamination of the surface of a metal port contaminated by tritium and apparatus usable for this process |
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| CN1986904A (en) | 2007-06-27 |
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