GB1572867A - Method for chemical decontamination of structural parts - Google Patents
Method for chemical decontamination of structural parts Download PDFInfo
- Publication number
- GB1572867A GB1572867A GB909377A GB909377A GB1572867A GB 1572867 A GB1572867 A GB 1572867A GB 909377 A GB909377 A GB 909377A GB 909377 A GB909377 A GB 909377A GB 1572867 A GB1572867 A GB 1572867A
- Authority
- GB
- United Kingdom
- Prior art keywords
- decontamination
- solution
- structural parts
- treatment
- oxidising
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C23—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; CHEMICAL SURFACE TREATMENT; DIFFUSION TREATMENT OF METALLIC MATERIAL; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL; INHIBITING CORROSION OF METALLIC MATERIAL OR INCRUSTATION IN GENERAL
- C23G—CLEANING OR DE-GREASING OF METALLIC MATERIAL BY CHEMICAL METHODS OTHER THAN ELECTROLYSIS
- C23G1/00—Cleaning or pickling metallic material with solutions or molten salts
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/001—Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
- G21F9/002—Decontamination of the surface of objects with chemical or electrochemical processes
- G21F9/004—Decontamination of the surface of objects with chemical or electrochemical processes of metallic surfaces
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Materials Engineering (AREA)
- Organic Chemistry (AREA)
- Metallurgy (AREA)
- Mechanical Engineering (AREA)
- Electrochemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- Food Science & Technology (AREA)
- Cleaning And De-Greasing Of Metallic Materials By Chemical Methods (AREA)
- Cleaning By Liquid Or Steam (AREA)
Abstract
A process for the chemical decontamination of nuclear reactor components in two steps comprises an approximately one hour-long oxidative pretreatment with an alkaline permanganate solution and, after intermediate rinsing with deionised water, pickling with an inhibited citrate-oxalate decontamination solution which has a pH set to approximately 3.5 and is applied for from 5 to 20 hours. The temperatures in the process, as well as during the final rinsing with deionized water, are at 95-100 DEG C.
Description
(54) A METHOD FOR CHEMICAL DECONTAMINATION
OF STRUCTURAL PARTS
(71) We, KRAFTWERK UNION
AKTIENGESELLSCHAFT, a German company of 433 Miilheim (Ruhr),
Wiesenstrasse 35, Germany, do hereby declare the invention, for which we pray that a patent may be granted to us and the method by which it is to be performed, to be particularly described in and by the following statement:- The present invention relates to a method for chemical decontamination of structural parts in two stages.
In water-cooled nuclear reactor for example, after a short running period, a cohesive dense oxide layer forms in the primary circulation of a nuclear power plant as a result of corrosion of the structural materials. This initially inactive oxide layer is contaminated during operation even in components which do not lie in the direct radiation field of the nuclear zone, thus becoming radioactive. This contamination can be attributed to the incorporation of activated corrosion products into the oxide layer of the structural materials. Since this process runs continuously, the result is a concentration, particularly of long-lived nuclides, in the oxide layer. It is therefore imperative that possibilities of eliminating this surface contamination by suitable decontaminating agents be sought.This demand becomes more and more pressing as the running period increases, as maintenance of the installations and above all repair work result in ever increasing radiation loading of the operating personnel.
Attempts have been made hitherto to decontaminate contaminated surfaces with aqueous solutions of mineral and organic acids. The- results thereby obtained, however, were totally inadequate since damage to the structural material itself, particularly, was caused at the same time.
Only the two stage APAC method (Alkaline - Permanganate - Ammonium
Citrate) provided a good degree of decontamination, but it similarly resulted in selective corrosion phenomena and, depending on the structural material, to unduly high base metal attacks.
According to the present invention there is provided a method for the chemical decontamination of structural parts, wherein the structural parts are subjected to a preliminary oxidising treatment with an alkaline permanganate solution and are then corroded with an inhibited citrateoxalate decontamination solution having a pH value of 3.5+0.5.
Preferably, the structural parts are rinsed with a deionate between the oxidising treatment and the corrosion treatment.
The structural parts may be subjected to the oxidising treatment for substantially one hour.
The alkaline permanganate solution is preferably at a temperature of from 95 to 100"C.
Preferably, the structural parts are corroded for from 5 to 20 hours.
Preferably, the pH of the decontamination solution is substantially 3.5.
The decontamination solution may contain the following substances added to each 1000 ml water:
50 g di-ammonium hydrogen citrate;
40 g oxalic acid;
4 g ethylenediamine tetraacetic acid;
5 g Fe-III-Formate;
together with sufficient ammonia to bring the pH of the solution to substantially 3.5.
The first three constituents represent a combination of complexing agents and organic acids; with these the decontamination factor is increased.
The decontamination solution is preferably at a temperature of from 95 to 100"C.
Preferably, the structural parts are rinsed with deionate after the corrosion treatment.
The permanganate solution may contain the following substances added to each 1000 ml water:
10 g sodium hydroxide solution; and
5 g potassium permanganate.
Preferably, the decontamination solution
is inhibited by means of di- and tri- valent metal salts of organic acids. The inhibitor may be, for example, a temperature resistant inhibitor in the form of Fe-II and
Fe-III salts of organic acids and is added to prevent attack on the base material thus preventing selective damage to the structural materials.
With the preliminary oxidising treatment and subsequent corrosion by the decontamination solution, radioactive materials may be brought to the following dose rate values within 1" -20 hours: Austenite 1.4550 from 1000 mR/h to 0.1 lmR/h Inconel 600 from 150 mR/h to 0.5-1 mR/h
Inconel X 750 from 300 mR/h to 0.5-1 mR/h
(Inconel is a Registered Trade Mark)
Subsequent metallographic tests on these
substances show that the decontamination treatment according to the invention does
not cause selective damage of any kind to
occur on these substances. The loss of
material was less than 0.1y in all cases.
Similar results were obtained in the decontamination of other substances such
as, for instance, Incoloy 800, Incoloy 901,
chromium steel 1,4523 and deposit weldings
(Incoloy is a Registered Trade Mark).
As already mentioned in the introduction,
decontamination of this type is often
necessary on parts of the primary
circulation system, such as pipelines, steam generators etc. so that repairs can be carried
out without an unduly high radiation load.
Obviously it is not necessary to treat the entire primary circulation system in this way, on the contrary it is sufficient to decontaminate the areas in the vicinity of the repair sites. All that is needed for this are blocking devices insertable from the exterior and which rest against the inner pipe walls, forming a seal, with the aid, for instance, of compressed air. Obviously the seal could also be made with the aid of purely mechanical means via elastic and acid resistant plastic seals.
Since the decontamination solutions used have themselves become radioactive, these must be discarded as radioactive waste. It is important here that a considerable reduction in volume of the used solutions may be obtained. In the present case, the two solutions, i.e. the oxidising solution and the decontamination solution are mixed together, by which the oxalic acid is oxidised to CO2 and KMnO4 reduced to
Mn. With a mixture ratio of 1:1, a solution pretreated in this way may be concentrated by vaporisation by about 80% without it resulting in the precipitation of salts. For the further processing of this concentrate up to final storage, further chemical and physical methods, known per se, may be used.
The method according to the invention thus makes not only thorough decontamination of radioactively contaminated nuclear reactor structural parts possible, and virtually without any adverse effect on the base material, but also relatively simple concentration of the used solutions.
WHAT WE CLAIM IS:
1. A method for the chemical decontamination of structural parts, wherein the structural parts are subjected to a preliminary oxidising treatment with an alkaline permanganate solution and are then corroded with an inhibited citrateoxalate decontamination solution having a pH value of 3.5+0.5.
2. A method according to claim 1, wherein the structural parts are rinsed with a deionate between the oxidising treatment and the corrosion treatment.
3. A method according to claim 1 or 2, wherein the structural parts are subjected to the oxidising treatment for substantially one hour.
4. A method according to claim 1, 2 or 3, wherein the alkaline permanganate solution is at a temperature of from 95 to 1000C.
5. A method according to any preceding claim, wherein the structural parts are corroded for from 5 to 20 hours.
6. A method according to any preceding claim, wherein the pH of the decontamination solution is substantially 3.5.
7. A method according to claim 6, wherein the decontamination solution contains the following substances added to each 1000 ml water:
50 g di-ammonium hydrogen citrate;
40 g oxalic acid;
4 g ethylenediamine tetraacetic acid;
5 g Fe-III-formate; together with sufficient ammonia to bring the pH of the solution to subtantially 3.5.
8. A method according to any preceding claim, wherein the decontamination solution is at a temperature of from 95 to 100"C.
**WARNING** end of DESC field may overlap start of CLMS **.
Claims (12)
- **WARNING** start of CLMS field may overlap end of DESC **.The permanganate solution may contain the following substances added to each 1000 ml water:10 g sodium hydroxide solution; and5 g potassium permanganate.Preferably, the decontamination solution is inhibited by means of di- and tri- valent metal salts of organic acids. The inhibitor may be, for example, a temperature resistant inhibitor in the form of Fe-II and Fe-III salts of organic acids and is added to prevent attack on the base material thus preventing selective damage to the structural materials.With the preliminary oxidising treatment and subsequent corrosion by the decontamination solution, radioactive materials may be brought to the following dose rate values within 1" -20 hours: Austenite 1.4550 from 1000 mR/h to 0.1 lmR/h Inconel 600 from 150 mR/h to 0.5-1 mR/h Inconel X 750 from 300 mR/h to 0.5-1 mR/h (Inconel is a Registered Trade Mark) Subsequent metallographic tests on these substances show that the decontamination treatment according to the invention does not cause selective damage of any kind to occur on these substances. The loss of material was less than 0.1y in all cases.Similar results were obtained in the decontamination of other substances such as, for instance, Incoloy 800, Incoloy 901, chromium steel 1,4523 and deposit weldings (Incoloy is a Registered Trade Mark).As already mentioned in the introduction, decontamination of this type is often necessary on parts of the primary circulation system, such as pipelines, steam generators etc. so that repairs can be carried out without an unduly high radiation load.Obviously it is not necessary to treat the entire primary circulation system in this way, on the contrary it is sufficient to decontaminate the areas in the vicinity of the repair sites. All that is needed for this are blocking devices insertable from the exterior and which rest against the inner pipe walls, forming a seal, with the aid, for instance, of compressed air. Obviously the seal could also be made with the aid of purely mechanical means via elastic and acid resistant plastic seals.Since the decontamination solutions used have themselves become radioactive, these must be discarded as radioactive waste. It is important here that a considerable reduction in volume of the used solutions may be obtained. In the present case, the two solutions, i.e. the oxidising solution and the decontamination solution are mixed together, by which the oxalic acid is oxidised to CO2 and KMnO4 reduced to Mn. With a mixture ratio of 1:1, a solution pretreated in this way may be concentrated by vaporisation by about 80% without it resulting in the precipitation of salts. For the further processing of this concentrate up to final storage, further chemical and physical methods, known per se, may be used.The method according to the invention thus makes not only thorough decontamination of radioactively contaminated nuclear reactor structural parts possible, and virtually without any adverse effect on the base material, but also relatively simple concentration of the used solutions.WHAT WE CLAIM IS: 1. A method for the chemical decontamination of structural parts, wherein the structural parts are subjected to a preliminary oxidising treatment with an alkaline permanganate solution and are then corroded with an inhibited citrateoxalate decontamination solution having a pH value of 3.5+0.5.
- 2. A method according to claim 1, wherein the structural parts are rinsed with a deionate between the oxidising treatment and the corrosion treatment.
- 3. A method according to claim 1 or 2, wherein the structural parts are subjected to the oxidising treatment for substantially one hour.
- 4. A method according to claim 1, 2 or 3, wherein the alkaline permanganate solution is at a temperature of from 95 to 1000C.
- 5. A method according to any preceding claim, wherein the structural parts are corroded for from 5 to 20 hours.
- 6. A method according to any preceding claim, wherein the pH of the decontamination solution is substantially 3.5.
- 7. A method according to claim 6, wherein the decontamination solution contains the following substances added to each 1000 ml water:50 g di-ammonium hydrogen citrate;40 g oxalic acid;4 g ethylenediamine tetraacetic acid;5 g Fe-III-formate; together with sufficient ammonia to bring the pH of the solution to subtantially 3.5.
- 8. A method according to any preceding claim, wherein the decontamination solution is at a temperature of from 95 to 100"C.
- 9. A method according to any precedingclaim, wherein the structural parts are rinsed with deionate after the corrosion treatment.10. A method according to any preceding claim, wherein the permanganate solution contains the following substances added to each 1000 ml water:
- 10 g sodium hydroxide solution; and5 g potassium permangante.
- 11. A method according to any preceding claim, wherein the decontamination solution is inhibited by means of di- and trivalent metal salts of organic acids.
- 12. A method for the chemical decontamination of structural parts according to claim 1 and substantially as hereinbefore described.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19762613351 DE2613351C3 (en) | 1976-03-29 | 1976-03-29 | Process for the chemical decontamination of metallic components of nuclear reactor plants |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1572867A true GB1572867A (en) | 1980-08-06 |
Family
ID=5973754
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB909377A Expired GB1572867A (en) | 1976-03-29 | 1977-03-03 | Method for chemical decontamination of structural parts |
Country Status (5)
Country | Link |
---|---|
JP (1) | JPS608479B2 (en) |
CH (1) | CH626741A5 (en) |
DE (1) | DE2613351C3 (en) |
FR (1) | FR2346819A1 (en) |
GB (1) | GB1572867A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5527445A (en) * | 1993-11-16 | 1996-06-18 | Ontario Hydro | Process and apparatus for in situ electroforming a structural layer of metal bonded to an internal wall of a metal tube |
CN113737191A (en) * | 2021-08-19 | 2021-12-03 | 中国辐射防护研究院 | Decontamination method of low-carbon martensite nickel-chromium stainless steel |
Families Citing this family (18)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2847780C2 (en) * | 1978-11-03 | 1984-08-30 | Kraftwerk Union AG, 4330 Mülheim | Process for the chemical decontamination of metallic components of nuclear reactor plants |
JPS5813879B2 (en) * | 1979-02-20 | 1983-03-16 | 日立造船株式会社 | Cask decontamination method |
DE2910708C2 (en) * | 1979-03-19 | 1986-07-24 | Kraftwerk Union AG, 4330 Mülheim | Method for cleaning a mixing device for embedding radioactive waste in heated bitumen |
EP0032416B2 (en) * | 1980-01-08 | 1987-06-16 | Central Electricity Generating Board | Descaling process |
JPS58174900A (en) * | 1982-04-07 | 1983-10-13 | 三菱重工業株式会社 | Method of decontaminating reactor component |
JPS5937498A (en) * | 1982-08-25 | 1984-02-29 | 株式会社日立製作所 | Atomic power plant provided with adhesion preventive function of radioactive material |
US4587043A (en) * | 1983-06-07 | 1986-05-06 | Westinghouse Electric Corp. | Decontamination of metal surfaces in nuclear power reactors |
DE3578635D1 (en) * | 1984-10-31 | 1990-08-16 | Kraftwerk Union Ag | METHOD FOR CHEMICAL DECONTAMINATION OF LARGE COMPONENTS AND SYSTEMS MADE OF METAL MATERIALS OF CORE REACTORS. |
FR2585817B1 (en) * | 1985-08-05 | 1989-08-25 | Framatome Sa | SURFACE TREATMENT METHOD AND DEVICE FOR HEAT EXCHANGERS |
BE904139A (en) * | 1986-01-30 | 1986-05-15 | Lemmens Godfried | PROCESS FOR THE DECONTAMINATION OF RADIOACTIVALLY CONTAMINATED MATERIALS. |
GB8613522D0 (en) * | 1986-06-04 | 1986-07-09 | British Nuclear Fuels Plc | Technetium decontamination |
JP2507478B2 (en) * | 1987-09-28 | 1996-06-12 | 株式会社東芝 | Decontamination system for radioactive waste |
EP0355628B1 (en) * | 1988-08-24 | 1993-11-10 | Siemens Aktiengesellschaft | Process for chemically decontaminating the surface of a metallic construction element of a nuclear power plant |
FR2644618B1 (en) * | 1989-03-14 | 1994-03-25 | Commissariat A Energie Atomique | METHOD FOR DECONTAMINATION OF METAL SURFACES, PARTICULARLY OF CONSTITUENT PARTS OF A NUCLEAR PRESSURE WATER REACTOR, AND DECONTAMINATION SOLUTIONS USED IN THIS PROCESS |
DE4131766A1 (en) * | 1991-09-24 | 1993-03-25 | Siemens Ag | Decontamination of nuclear power station prim. cycle to remove metal oxide - by adding chelating agent to prim. coolant to dissolve contaminated oxide |
DE19546789A1 (en) * | 1995-12-14 | 1997-06-19 | Siemens Ag | Process for recycling contaminated metal parts |
DE19851852A1 (en) * | 1998-11-10 | 2000-05-11 | Siemens Ag | Process for the decontamination of a surface of a component |
JP3977963B2 (en) | 1999-09-09 | 2007-09-19 | 株式会社日立製作所 | Chemical decontamination method |
-
1976
- 1976-03-29 DE DE19762613351 patent/DE2613351C3/en not_active Expired
-
1977
- 1977-03-03 GB GB909377A patent/GB1572867A/en not_active Expired
- 1977-03-07 CH CH278977A patent/CH626741A5/en not_active IP Right Cessation
- 1977-03-28 FR FR7709221A patent/FR2346819A1/en active Granted
- 1977-03-29 JP JP3515077A patent/JPS608479B2/en not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5527445A (en) * | 1993-11-16 | 1996-06-18 | Ontario Hydro | Process and apparatus for in situ electroforming a structural layer of metal bonded to an internal wall of a metal tube |
US5538615A (en) * | 1993-11-16 | 1996-07-23 | Ontario Hydro | Metal tube having a section with an internal electroformed structural layer |
CN113737191A (en) * | 2021-08-19 | 2021-12-03 | 中国辐射防护研究院 | Decontamination method of low-carbon martensite nickel-chromium stainless steel |
Also Published As
Publication number | Publication date |
---|---|
FR2346819A1 (en) | 1977-10-28 |
JPS52118200A (en) | 1977-10-04 |
CH626741A5 (en) | 1981-11-30 |
FR2346819B1 (en) | 1982-11-19 |
DE2613351A1 (en) | 1977-10-13 |
DE2613351C3 (en) | 1982-03-25 |
JPS608479B2 (en) | 1985-03-02 |
DE2613351B2 (en) | 1981-07-16 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |