EP0224510A1 - Verfahren zur dekontamination von radioaktiv kontaminierten gegenständen aus metall oder aus zementhaltigem material. - Google Patents
Verfahren zur dekontamination von radioaktiv kontaminierten gegenständen aus metall oder aus zementhaltigem material.Info
- Publication number
- EP0224510A1 EP0224510A1 EP86903176A EP86903176A EP0224510A1 EP 0224510 A1 EP0224510 A1 EP 0224510A1 EP 86903176 A EP86903176 A EP 86903176A EP 86903176 A EP86903176 A EP 86903176A EP 0224510 A1 EP0224510 A1 EP 0224510A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- decontamination
- acid
- agent
- solution
- decontamination agent
- 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.)
- Granted
Links
Classifications
-
- 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
Definitions
- the present invention relates to an agent for the decontamination of contaminated metallic or cement-containing materials.
- the invention also relates to a method for producing this decontamination agent using boric acid, which is contained in primary circuits of pressurized water reactors.
- the invention further relates to methods of using the decontaminant.
- the decontamination agent according to the invention is not restricted to the use of radioactively contaminated materials, the main emphasis in the following is placed on this application.
- the contaminated metal surface is treated with a cerium salt solution containing at least one cerium IV salt and a water-containing solvent.
- a cerium salt solution containing at least one cerium IV salt and a water-containing solvent.
- Another decontamination process is described in EP application, publication no. 00 73 366, in which an aqueous solution of formic acid and / or acetic acid and a reduction is used as the decontamination agent medium, especially formaldehyde and / or acetaldehyde, is used.
- a relatively low need for chemicals is of particular advantage and, when disposing of the used decontamination solution, an amount of radioactive substances corresponding approximately to the volume of the removed surface layers.
- the basic concept is based on the fact that the activity in the contaminated surface layer decreases with the mass as the surface layer itself is detached by the decontamination solution.
- the depth of penetration of active material into the surface layer can be determined or measured before decontamination, which then results in the thickness of the surface layer to be removed in order to achieve a certain final decontamination state.
- boric acid in concentrations up to 3000 ppm. During the operation of such reactors, smaller amounts of the liquid mentioned are produced as waste. In addition to boric acid, this waste also contains contaminants such as cobalt compounds, as well as solid contaminants such as rust residues, fabric fibers, dust, etc. In certain cases, this waste can even be treated to such an extent that it Form of a solid material.
- This object is achieved by a decontamination agent according to claim 1, which can be obtained according to the method according to claim 6 and which allows use according to claim 9. Variations of the agent, its method of manufacture and its use emerge from the dependent claims and are explained in the description.
- the device for carrying out the present method ( Figure 1) has a container for holding the objects to be decontaminated.
- the duration of treatment of objects in the receptacle 1 is selected so that the objects are free of radioactivity after the end of the method. Such objects are then removed from the receptacle 1 and can then either be reused or sent to the scrap.
- a decontamination solution is introduced into the receptacle 1, which acts on the surface of the objects in such a way that the contaminated surface layer is dissolved and removed.
- the decontamination solution in container 1 can form a bath in which the items are located, or the decontamination solution is sprayed into container 1.
- a circulating device 2 with a pump can be assigned to the receiving container 1. This makes it possible to achieve a long treatment time for the objects with a relatively small amount of the decontamination solution.
- An evaporator 3 is connected to the receptacle 1 via a line 4. In the evaporator 3, more volatile components of a concentrated solution are separated from less volatile components thereof. Vaporizable components are fed to an absorber 6 through a further line 5.
- the sump products from the evaporator 3 are transferred to a reduction device 7, in which they are reduced to metallic iron, chromium, nickel, lead, etc.
- the reduction device 7 is connected via a line 9 to the absorber 6, through which HF is led from the reduction device 7 to the absorber 6.
- the hydrogen required for the reduction of metal compounds can be fed to the reduction device 7 through a line 10 from the dissolver 1.
- An electrolytic cell 12 can be connected to the receiving container 1 via a line 13, through which the concentrated solution is pumped out of the receiving container 1 into the cell 12. During the operation of this cell 12, BF 4 ions are recombined to HBF 4 at the anode. HBF 4 is fed to the receptacle 1 through a further line 14.
- Line 15 is fed to the receptacle 1.
- the quality of the surface of the treated objects can be influenced during and / or after decontamination by surface-active substances.
- Wetting agents such as e.g. Soaps, water permeability inhibitors, such as. B. formaldehyde, etc. in question.
- the dissolver 1 (sprinkler system), in which the objects to be decontaminated are placed in a bath for free decontamination or for free measurement or are sprayed using a spray process.
- the second part of the process consists of evaporation in an evaporator 3.
- BF 3 , HBF 4 , H 2 O and dehydrates of boric acid are evaporated, suctioned off and dissolved in the liquid phase in the next part of the plant, the absorber 6.
- the solution obtained is mixed with hydrofluoric acid or with hydrofluoric acid vapors for the production of fresh HBF 4 acid, which is fed to the dissolver 1.
- the soup products from the evaporator 3 are transferred to the reduction part 7 of the installation, in which they can be reduced to metallic iron, chromium or nickel (among others).
- disposal methods can be used: a) the direct disposal of the decontamination agent from the dissolver 1, b) the disposal of fluorides in the evaporated form, c) the disposal of metallic components after reductions, d) or their combinations .
- Absorption capacity of the decontamination agent or decontamination solution 1 liter can dissolve up to 220 grams of stainless steel at 90 ° C, allows high area-related decontamination lines. Such a high absorption capacity allows to decontaminate approx. 30 m 2 of the surface with only 1 liter of decontamination solution with a removal of 1 micrometer.
- a concentration of up to 220 grams of stainless steel per liter at 90 ° C can be achieved.
- This concentrated solution is pumped into the electrolytic cell 12, where metal is excreted at the cathode, while BF 4 ions recombine at the anode to HBF 4 and this is returned to the decontamination process.
- iron-containing Fe (BF 4 ) 2 concentrate is discussed as an example. This concentrate also contains radioactivity, but this does not affect the chemical balance. Detached stainless steel, nickel-based alloys and other contaminated materials can be treated analogously. The following equation can be used for the direct disposal of iron concentrates:
- Iron, chromium, nickel or copper is removed electrolytically from the iron-containing concentrate and then mixed with cement.
- the electrolysis proceeds as follows:
- Dissolver 1 Fe + 2 HBF 4 --------- ⁇ Fe (BF 4 ) 2 + H 2
- Evaporator 3 : a) distill off H 2 O b) distill off unreag. HBF 4
- Ni (BF 4 ) 2 NiF 2 + 2 BF 3
- Fe (Si F 6 ) 2 Fe F 2 + 2 Si F 4 (pyrolysis) in general.
- Me n + (Si F 6 ) n Me F n + n Si F 4
- the object of the present invention is to eliminate the mentioned but also further disadvantages of the prior art in the field of decontamination. This object is achieved according to the invention in the method of the type mentioned at the outset as defined in the characterizing part of claim 1.
- the masonry surface is misted / moistened with HBF 4 and / or H 2 SiF 6 acid.
- the chemical reaction between the carbonates in masonry and the acids produces gaseous CO 2 .
- the gas bubbles form a foam with the acid, which is an excellent flotation agent for the contaminants.
- the foam is then suctioned off with the activity.
- Fluorine ions from the fluorocomplexes of the acids react with the calcium present and form an insoluble, voluminous precipitate of CaF 2 , which clogs the pores on the surface.
- the impregnation of the masonry described massively impedes the transport of activity into the interior of the material. With radium-contaminated concrete, decofactors between 10 and 15 were achieved during decontamination.
- the device for carrying out the present method contains a reaction container 1, in which contaminated boric acid is converted into an easily evaporable boron compound ( Figure 2). Contaminated boric acid is introduced into the reaction vessel 1 through a first line 2.
- a chemical substance is supplied to the reaction vessel 1, which causes the conversion mentioned. It can be gaseous fluorine or hydrofluoric acid. Hydrofluoric acid can be used either in the form of liquid or in the form of gas.
- a pump 4 is connected to the reaction container 2 and conveys the reaction product from the reaction vessel 1 into a distillation device 5 of a type known per se.
- the speed at which the two components mentioned are introduced through lines 2 and 3 into the reaction vessel 1 and the rate at which the reaction product is withdrawn from the reaction vessel 1 is selected so that the material supplied is given sufficient time for the reaction to proceed to completion.
- the sump that remains in the distillation device 5 is removed from it and conditioned for disposal.
- the sump is first neutralized in a further vessel 6, for example with calcium hydroxide.
- the neutralized sump material can only be dried and then immediately deposited. However, it can also be solidified with cement or bitumen and only then deposited.
- the thermal energy required for the distillation in the device 5 is advantageously taken from liquid or gaseous media.
- the distillation is advantageously carried out under reduced pressure because the temperatures in the device 5 are then relatively low and at such temperatures virtually no pyrolysis can take place.
- the HBF 4 acid obtained during the distillation is led out of the distillation device 5 through a line 6.
- This acid can be used as a fully regenerable decontamination agent as described in Swiss patent application No. 2238/85 by the same applicant, or the acid can be sold to the chemical industry, where it can be used, for example, in electroplating.
- the borofluoric acid which is produced during the distillation, does not end up in the repository for radioactive material, but can be sold, for example, to the chemical industry and can therefore be used further.
- the swamp because it now has a smaller volume, can be disposed of, without causing great costs.
- the present process is based on the knowledge that, in contrast to H 3 BO 3 , borofluoric acid HBF 4 can be distilled and can thus be separated from the contaminants, such as, for example, Co-60 Cs nuclides.
- the borofluoric acid can be separated into fractions of different densities during distillation.
- the principle reactions on which the present method is based are as follows:
- the HBF 4 acid obtained may also contain traces of activity (in the single-stage distillation) because it can be used as a completely regenerable decontamination agent for components made from DWR and SWR.
- the option for an inactive use is to carry out a multi-stage distillation.
Description
Claims
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
AT86903176T ATE60160T1 (de) | 1985-05-28 | 1986-05-27 | Verfahren zur dekontamination von radioaktiv kontaminierten gegenstaenden aus metall oder aus zementhaltigem material. |
Applications Claiming Priority (6)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CH223985 | 1985-05-28 | ||
CH223885 | 1985-05-28 | ||
CH2238/85 | 1985-05-28 | ||
CH2239/85 | 1985-05-28 | ||
CH232885 | 1985-06-03 | ||
CH2328/85 | 1985-06-03 |
Publications (2)
Publication Number | Publication Date |
---|---|
EP0224510A1 true EP0224510A1 (de) | 1987-06-10 |
EP0224510B1 EP0224510B1 (de) | 1991-01-16 |
Family
ID=27173548
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP86903176A Expired - Lifetime EP0224510B1 (de) | 1985-05-28 | 1986-05-27 | Verfahren zur dekontamination von radioaktiv kontaminierten gegenständen aus metall oder aus zementhaltigem material |
Country Status (4)
Country | Link |
---|---|
US (3) | US4828759A (de) |
EP (1) | EP0224510B1 (de) |
DE (1) | DE3676962D1 (de) |
WO (1) | WO1986007184A1 (de) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5414196A (en) * | 1991-10-18 | 1995-05-09 | British Nuclear Fuels Plc | Method of decontaminating a cementitious surface |
Families Citing this family (26)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS6432197A (en) * | 1987-07-29 | 1989-02-02 | Hitachi Ltd | Plant for retreatment of nuclear fuel |
DE58904254D1 (de) * | 1988-07-28 | 1993-06-09 | Siemens Ag | Elektropolierverfahren zum zwecke der dekontamination. |
CH678767A5 (de) * | 1989-06-30 | 1991-10-31 | Jozef Hanulik Dipl Chem | |
CH682023A5 (de) * | 1990-10-26 | 1993-06-30 | Recytec Sa | |
US5154899A (en) * | 1991-06-28 | 1992-10-13 | Sturcken Edward F | Metal recovery from porous materials |
US5205999A (en) * | 1991-09-18 | 1993-04-27 | British Nuclear Fuels Plc | Actinide dissolution |
DE4216383A1 (de) * | 1992-05-18 | 1993-11-25 | Siemens Ag | Verfahren zum Reinigen eines geschlossenen Behälters |
EP0610153B1 (de) * | 1993-02-01 | 1996-09-25 | Deco-Hanulik Ag | Verfahren zur Dekontamination von radioaktiven Metalloberflächen |
US5545795A (en) * | 1993-02-01 | 1996-08-13 | Deco-Hanulik Ag | Method for decontaminating radioactive metal surfaces |
EP0614196A1 (de) * | 1993-03-01 | 1994-09-07 | Deco-Hanulik Ag | Verfahren zur Reinigung kontaminierter Oberflächen aus mineralischen Materialien, sowie Vorrichtung zur Durchführung des Verfahrens |
TW288145B (de) * | 1994-02-01 | 1996-10-11 | Toshiba Co Ltd | |
DE4420139C1 (de) * | 1994-06-09 | 1995-12-07 | Kraftanlagen En Und Industriea | Verfahren zur elektrochemischen Dekontamination von radioaktiv belasteten Oberflächen von Metallkomponenten aus kerntechnischen Anlagen |
US5635143A (en) * | 1994-09-30 | 1997-06-03 | Martin Marietta Energy Systems, Inc. | Mobile system for microwave removal of concrete surfaces |
GB9422539D0 (en) * | 1994-11-04 | 1995-01-04 | British Nuclear Fuels Plc | Decontamination processes |
US5525236A (en) * | 1995-04-12 | 1996-06-11 | Wilkinson; Kenneth | Reverse osmosis purification of water |
US5724668A (en) * | 1995-11-07 | 1998-03-03 | Electronic Power Research Institute | Method for decontamination of nuclear plant components |
US5752206A (en) * | 1996-04-04 | 1998-05-12 | Frink; Neal A. | In-situ decontamination and recovery of metal from process equipment |
US6147274A (en) * | 1996-11-05 | 2000-11-14 | Electric Power Research Insitute | Method for decontamination of nuclear plant components |
US5901368A (en) * | 1997-06-04 | 1999-05-04 | Electric Power Research Institute | Radiolysis-assisted decontamination process |
US6682646B2 (en) * | 2002-03-25 | 2004-01-27 | Electric Power Research Institute | Electrochemical process for decontamination of radioactive materials |
US8165261B2 (en) * | 2008-01-22 | 2012-04-24 | Electric Power Research Institute, Inc. | Chemical enhancement of ultrasonic fuel cleaning |
US20100072059A1 (en) * | 2008-09-25 | 2010-03-25 | Peters Michael J | Electrolytic System and Method for Enhanced Radiological, Nuclear, and Industrial Decontamination |
GB2499025A (en) * | 2012-02-03 | 2013-08-07 | Nat Nuclear Lab Ltd | Decontamination of a system and treatment of the spent decontamination fluid |
TWI525048B (zh) * | 2013-04-26 | 2016-03-11 | 行政院原子能委員會核能研究所 | 放射性廢酸液之回收方法 |
DE102016208202A1 (de) * | 2016-05-12 | 2017-11-16 | Rwe Power Aktiengesellschaft | Chemische Dekontamination von radioaktiven Metalloberflächen |
RU2671243C1 (ru) * | 2017-10-30 | 2018-10-30 | Акционерное общество "Радиевый институт им. В.Г. Хлопина" | Способ переработки битумно-солевых радиоактивных компаундов |
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GB891670A (en) * | 1957-09-04 | 1962-03-14 | English Electric Co Ltd | Improvements in and relating to the removing of scale from silicon iron and other metals |
BE670521A (de) * | 1964-10-05 | 1900-01-01 | ||
US3341304A (en) * | 1966-04-08 | 1967-09-12 | Billie J Newby | Separation of uranium from uranium dioxide-zirconium dioxide mixtures |
US3409413A (en) * | 1967-08-11 | 1968-11-05 | Atomic Energy Commission Usa | Method of dissolving aluminum-clad thoria target elements |
US3565707A (en) * | 1969-03-03 | 1971-02-23 | Fmc Corp | Metal dissolution |
DE2058766A1 (de) * | 1970-11-30 | 1972-05-31 | Siemens Ag | Verfahren zur Reinigung von metallischen Oberflaechen,insbesondere radioaktiv verseuchten Oberflaechen |
US3891741A (en) * | 1972-11-24 | 1975-06-24 | Ppg Industries Inc | Recovery of fission products from acidic waste solutions thereof |
US3986970A (en) * | 1973-05-02 | 1976-10-19 | The Furukawa Electric Co., Ltd. | Solution for chemical dissolution treatment of tin or alloys thereof |
US3873362A (en) * | 1973-05-29 | 1975-03-25 | Halliburton Co | Process for cleaning radioactively contaminated metal surfaces |
US3965237A (en) * | 1975-04-11 | 1976-06-22 | The United States Of America As Repesented By The United States Energy Research And Development Administration | Dissolution process for ZrO2 -UO2 -CaO fuels |
DE2553569C2 (de) * | 1975-11-28 | 1985-09-12 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Verfahren zur Verfestigung von radioaktiven wäßrigen Abfallstoffen durch Sprühkalzinierung und anschließende Einbettung in eine Matrix aus Glas oder Glaskeramik |
BE838533A (fr) * | 1976-02-13 | 1976-05-28 | Procede de sechage des solutions contenant de l'acide borique | |
CH619807A5 (de) * | 1976-04-07 | 1980-10-15 | Foerderung Forschung Gmbh | |
DE2910677C2 (de) * | 1979-03-19 | 1983-12-22 | Kraftwerk Union AG, 4330 Mülheim | Verfahren zur Behandlung von borhaltigen radioaktiven Konzentraten aus Abwässern von Druckwasserreaktoren |
US4217192A (en) * | 1979-06-11 | 1980-08-12 | The United States Of America As Represented By The United States Department Of Energy | Decontamination of metals using chemical etching |
US4443269A (en) * | 1979-10-01 | 1984-04-17 | Health Physics Systems, Inc. | Tool decontamination method |
CH653466A5 (de) * | 1981-09-01 | 1985-12-31 | Industrieorientierte Forsch | Verfahren zur dekontamination von stahloberflaechen und entsorgung der radioaktiven stoffe. |
US4686019A (en) * | 1982-03-11 | 1987-08-11 | Exxon Research And Engineering Company | Dissolution of PuO2 or NpO2 using electrolytically regenerated reagents |
US4530723A (en) * | 1983-03-07 | 1985-07-23 | Westinghouse Electric Corp. | Encapsulation of ion exchange resins |
US4620947A (en) * | 1983-10-17 | 1986-11-04 | Chem-Nuclear Systems, Inc. | Solidification of aqueous radioactive waste using insoluble compounds of magnesium oxide |
US4537666A (en) * | 1984-03-01 | 1985-08-27 | Westinghouse Electric Corp. | Decontamination using electrolysis |
US4701246A (en) * | 1985-03-07 | 1987-10-20 | Kabushiki Kaisha Toshiba | Method for production of decontaminating liquid |
-
1986
- 1986-05-27 WO PCT/CH1986/000069 patent/WO1986007184A1/de active IP Right Grant
- 1986-05-27 DE DE8686903176T patent/DE3676962D1/de not_active Expired - Fee Related
- 1986-05-27 US US07/019,799 patent/US4828759A/en not_active Expired - Fee Related
- 1986-05-27 EP EP86903176A patent/EP0224510B1/de not_active Expired - Lifetime
-
1989
- 1989-05-09 US US07/349,586 patent/US5008044A/en not_active Ceased
- 1989-05-09 US US07/349,284 patent/US4933113A/en not_active Expired - Fee Related
Non-Patent Citations (1)
Title |
---|
See references of WO8607184A1 * |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5414196A (en) * | 1991-10-18 | 1995-05-09 | British Nuclear Fuels Plc | Method of decontaminating a cementitious surface |
Also Published As
Publication number | Publication date |
---|---|
EP0224510B1 (de) | 1991-01-16 |
WO1986007184A1 (en) | 1986-12-04 |
US5008044A (en) | 1991-04-16 |
US4828759A (en) | 1989-05-09 |
US4933113A (en) | 1990-06-12 |
DE3676962D1 (de) | 1991-02-21 |
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