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EP4154279B1 - Procédé de décontamination liquide des objets contaminés radioactivement et retraitement d`eau du procédé - Google Patents

Procédé de décontamination liquide des objets contaminés radioactivement et retraitement d`eau du procédé Download PDF

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Publication number
EP4154279B1
EP4154279B1 EP21736546.9A EP21736546A EP4154279B1 EP 4154279 B1 EP4154279 B1 EP 4154279B1 EP 21736546 A EP21736546 A EP 21736546A EP 4154279 B1 EP4154279 B1 EP 4154279B1
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EP
European Patent Office
Prior art keywords
filter
process water
water
filter belt
pressure
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Active
Application number
EP21736546.9A
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German (de)
English (en)
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EP4154279C0 (fr
EP4154279A2 (fr
Inventor
Jörg RECKNAGEL
Klaus STEINBACHER
Benjamin Bauer
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RWE Nuclear GmbH
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RWE Nuclear GmbH
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Publication date
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Publication of EP4154279B1 publication Critical patent/EP4154279B1/fr
Publication of EP4154279C0 publication Critical patent/EP4154279C0/fr
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/001Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
    • G21F9/005Decontamination of the surface of objects by ablation
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing

Definitions

  • the subject of the present invention is a method for wet decontamination of radioactively contaminated workpieces using process water treatment.
  • surfaces can regularly be radioactively contaminated, with radioactive substances accumulating on them. If such contamination needs to be removed, for example as part of the dismantling of a nuclear facility, various methods are used, including wet decontamination.
  • the surfaces of workpieces to be cleaned are cleaned with liquid decontaminants by bringing the surface into contact with the liquid decontaminant, for example in the form of an immersion bath or by applying the liquid decontaminant to the surface under pressure.
  • Water-based liquid decontamination agents are regularly used.
  • the liquid decontamination agent can consist entirely of water, but other substances can also be added to the water that are tailored to the contaminating substances and/or the surface, for example soap or complexing agents that form complexes with certain radioactive substances or compounds for example, failures.
  • the aim of wet decontamination is at least to reduce the contamination of the workpiece, so that the liquid decontamination agent after wet decontamination (the process water) has radioactive contamination, so that the process water must be treated in order to contain the cleaned process to supply the delivery path for delivery,
  • many elements in nuclear facilities are coated, for example with a decont paint according to DIN 25415, in order to avoid contamination of the element and/or to make it easily removable during operation.
  • many elements in nuclear facilities can be coated multiple times. This is carried out in particular in order to close holes, cracks or the like in areas below the new coating, which can represent both an older coating and the surface of the element itself, since in the event of radioactive contamination, contaminated particles or accumulate substances.
  • the coatings of many elements have to be removed. Since these coatings are predominantly, if at all, only slightly radioactively contaminated, different processes are used here than for wet decontamination.
  • water-based process media preferably process water, can be used to strip the elements.
  • This process water is usually significantly less contaminated with radioactive contamination than the liquid decontamination agent after wet decontamination.
  • the liquid decontaminant after wet decontamination is usually subjected to a very complex preparation, which includes evaporation of the decontaminant to isolate radioactively contaminated particles.
  • the present invention is based on the object of at least partially overcoming the disadvantages known from the prior art.
  • decoating means the removal of one or more coatings that are applied to the surface of the coated element.
  • the coating in particular comprises a lacquer and/or is polymer-based.
  • High-pressure treatment means the application of process water to the surface of the coated element, which is discharged onto the surface under high pressure, in particular a pressure of 500 bar to 2500 bar.
  • the process water is preferably tempered to a temperature of up to 60°C.
  • Deionate i.e. demineralized water, is preferred as process water.
  • deionate is understood to mean, in particular, water with an electrical conductivity of 3 ⁇ S/cm [microSiemens per centimeter] or less, in particular 0.1 ⁇ S/cm or less.
  • the temperature control up to 60°C takes place in particular taking into account the heating of the process water when the pressure is relaxed from the high pressure mentioned to ambient pressure.
  • the process water is cooled to a temperature below the ambient temperature, in particular to 10 ° C and less.
  • the high-pressure treatment removes at least part of the coating in the form of particles. Since the coated element is or was part of a nuclear facility, radioactive contamination cannot be ruled out. The process water therefore contains particles that may possibly be radioactively contaminated.
  • the process water is treated.
  • the process water includes water, possibly solids, i.e. substances that are solid and therefore not dissolved in water, and possibly liquids that are not soluble in water, such as hydrocarbons such as oils.
  • the solids may be present as suspended matter, floating matter and/or bedload.
  • Suspended solids are solids contained in the process water that do not dissolve and are kept in suspension because of their small size and density similar to water.
  • Floating solids are solids contained in the process water that do not dissolve and float on the surface of the process water.
  • Bedloads are solids that sink down in the process water due to their density.
  • Both the solids and the dissolved chemical compounds and the liquids that are not soluble in the process water can contain radioisotopes.
  • the radioisotope concentration is reduced, so that the pure water can be released into a delivery path, for example into a wastewater treatment for later discharge into a body of water, for example into a river, or can be used again as process water for decoating, if necessary with the addition of fresh water or deionized water.
  • the pure water should fall below certain limit values, especially with regard to the particle load, the radiological activity, the electrical conductivity and/or the particle size distribution of the particles in the process water or pure water.
  • the high-pressure treatment of an element itself preferably includes the application of process water to a surface of the element, which is discharged under a pressure of in particular 500 bar to 2,500 bar and directed onto the surface. This can be done either by manually guiding a corresponding high-pressure lance or by using a corresponding manipulator, which automatically guides a high-pressure lance.
  • the process water is in particular deionized water.
  • the process water can preferably be tempered, with the temperature of the process water preferably being selected depending on the substances to be removed. A temperature range of 8° C to 60° C is preferred.
  • the vacuum filtration according to step a) is also referred to as vacuum belt filtration.
  • a filter belt made of a plastic, in particular an elastomer, is preferably used as the filter belt.
  • a multi-part filter belt can also be used, in which a movable carrying belt is provided with a porous filter element, for example a porous filter cloth.
  • the vacuum filtration can at least partially separate solids from the process water.
  • the coalescence deposition in step b) is based on a segregation phenomenon in which dispersed liquid drops, for example hydrocarbon drops, combine to form larger drops and in particular to form a colloid phase that can be removed from the process water.
  • This allows liquids with a lower density than water, in particular hydrocarbons such as oil, gasoline, alcohols, aromatics and/or certain other organic solvents, to be separated and removed from the process water.
  • Steps a) and b) can be carried out in any order.
  • the method according to the invention allows a decoating of potentially radioactively contaminated coated elements during treatment of the process water, which enables at least partial reuse of the process water for high-pressure treatment and/or discharge into bodies of water, without generating secondary waste.
  • steps a) and b) allow the process water to be treated without producing filter media that have to be disposed of due to being loaded with radioisotopes.
  • the filter belt is preferably moved in a rotating manner.
  • the filter cake can simply be separated from the filter belt while the filter belt is rotating, for example by a mechanical separating element such as a blade or the like, and transferred to the collecting container.
  • a mechanical separating element such as a blade or the like
  • UV radiation refers to ultraviolet electromagnetic radiation. UV radiation is understood to mean, in particular, electromagnetic radiation with a wavelength of 100 nm [nanometers] to 400 nm.
  • the radiation source is preferably a vapor lamp, such as at least one mercury vapor lamp and/or at least one LED (light-emitting diode) with corresponding radiation characteristics is used.
  • the particle load is understood to mean the mass of the particles contained in the respective liquid.
  • the particle size distribution is understood to mean the frequency distribution of a size of the particles.
  • the measured values obtained in i), ii), iii) and/or iv) can preferably be used to regulate the process, in particular with regard to the order of steps a) and b).
  • the process parameters of at least one of steps a) and b) are preferably changed depending on the results of at least one of the measurements carried out.
  • the speed at which the filter belt is moved and/or the negative pressure in the filter chamber can be changed based on the result of at least one of the measurements carried out.
  • the pure water is preferably used to carry out a high-pressure treatment. This means that the pure water can at least partially be used in a circuit.
  • step b) settling particles are preferably collected in a collecting container.
  • the process water flows at comparatively low flow velocities, which allows suspended solids to settle.
  • the collection container is used to collect such particles.
  • the collecting container is preferably funnel-shaped.
  • Particles present in the collecting container are preferably removed from it by a backwashing process. This enables easy and controlled removal of the particles.
  • first primarily serve (only) to distinguish between several similar objects, sizes or processes, i.e. in particular no dependency and/or order of these objects, sizes or prescribe processes to each other. If a dependency and/or sequence is required, this is explicitly stated here or it will be obvious to the person skilled in the art when studying the specifically described embodiment.
  • Fig. 1 shows very schematically the process sequence of the method described here for the treatment of a process water 10 of a decoating of a potentially radioactively contaminated coated element of a nuclear facility in a corresponding device 1.
  • the coated element can, for example, represent a pipe, a floor or wall element or the like.
  • the process water 10 is first fed as wastewater from a decoating (not shown) to a vacuum belt filter 100, which is particularly in connection with the Figures 2 and 3 is described in more detail.
  • the resulting filter cake 106 is fed to a collecting container 108, collected there and then later stored or stored temporarily.
  • the resulting filtrate 113 is fed to a coalescence separator 200, which is used in particular in connection with the Figures 4 and 5 is described in more detail.
  • the separated hydrocarbons 208 collected in the coalescence separator 200 are collected in a collection tank 205 in order to then be sent to intermediate or final storage.
  • the resulting filtrate 209 is fed to a filter unit 400 via a pure water tank 300.
  • the pure water created there 404 is fed to a pump template 600.
  • the process water is taken from the pump receiver 600 for the decoating operation.
  • the filter residue 405 resulting from backwashing in the filter unit 400 is fed again to the vacuum belt filter 100. Furthermore, depending on the operating state, precoat water 406 is backwashed from the filter unit 400 into the pure water tank 300.
  • the filter unit 400 will be discussed below in connection with Figures 4 and 5 described in more detail.
  • Figs. 2 and 3 show an example of a vacuum belt filter 100, also referred to as a vacuum belt filter, in various views.
  • Fig. 2 shows the operating principle of the vacuum belt filter 100
  • Fig. 3 a perspective view of the vacuum belt filter 100 shows.
  • the process water 10 is fed via a process water supply 101 into a process water feed 102, through which the process water 10 is applied to a filter belt 103.
  • the filter belt 103 is porous and is moved around two rollers 104.
  • the process water 10, including the load of solids contained therein, thus comes into contact with the filter belt 103.
  • the filter belt 103 has an upper side 105 and an underside 116 opposite the upper side 105.
  • the filter belt 103 is guided with the bottom 116 over a filter chamber 109, in which a negative pressure is generated, which drives the process water 10 from the top 105 through the filter belt 103, the process water 10 being guided so that it is with the top 105 of the Filter belt 103 comes into contact, so that the process water 10 is guided by the applied negative pressure from the top 105 through the filter belt 103 to the underside 116 of the filter belt 103, with at least some of the solids contained in the process water 10 remaining as filter cake 106 on the filter belt 103 .
  • the filter cake 106 is passed through the filter belt 103 to a filter cake separator 107 promoted, through which the filter cake 106 is transported into a collecting container 108.
  • the filter cake separator 107 is designed, for example, as a scraper, alternatively or additionally as at least one rotating brush.
  • the negative pressure in the filter chamber 109 is generated via a compressor 110, which is connected to the filter chamber 109 via a filtrate reservoir 111.
  • the compressor 110 is connected to a gas space 112 of the filtrate reservoir 111, which in turn is connected to the filter chamber 109.
  • the filtrate 113 i.e. the process water 10 freed from at least part of the load, collects in the filtrate reservoir 111 and can be removed from there from the filtrate reservoir 111 via a filtrate drain line 114.
  • the compressor 110 has a filter, not shown, in particular a HEPA filter, particularly preferably a HEPA filter of the H14 specification, on the suction side of the compressor 110, with which preferably (but not shown here) the air spaces of the vacuum belt filter 100, of Coalescence separator 200 and the pure water tank 300 are connected to prevent the breakthrough of radiologically contaminated aerosols.
  • a filter not shown, in particular a HEPA filter, particularly preferably a HEPA filter of the H14 specification, on the suction side of the compressor 110, with which preferably (but not shown here) the air spaces of the vacuum belt filter 100, of Coalescence separator 200 and the pure water tank 300 are connected to prevent the breakthrough of radiologically contaminated aerosols.
  • the vacuum band filter 100 also has fastening elements 115, via which radiation shielding elements, not shown, are fastened for shielding from ionizing radiation, in particular gamma radiation.
  • the radiation shielding elements include in particular lead.
  • the vacuum belt filter 100 has a filter residue task 110.
  • the filter residues 405 from the filter unit 400 can be applied to an area of the filter cake 106 that is no longer in contact with the process water 10. In this area is the filter cake 106 is completely built up in a cross-sectional direction, so that the solids in the filter residues 405 are filtered off efficiently.
  • Figs. 4 and 5 show further details of the device 1 Fig. 1 .
  • Fig. 4 shows a sectional view and Fig. 5 a perspective view.
  • the device 1 further comprises a coalescence separator 200, a pure water tank 300, a filter system 400 and a UV system 500, which are described below with reference to both figures.
  • the filtrate from the vacuum belt filter 100 is introduced into the coalescence separator 200 via a coalescence separator inlet 201.
  • the coalescing separator 200 is used to remove liquids with a density that is less than the density of water from the process water. These are in particular hydrocarbons such as alcohols and/or oils.
  • the coalescence separator 200 comprises a plurality of inclined plates 202. For the sake of clarity, only a single inclined plate 202 is shown, but a plurality of inclined plates 202 are formed, which are aligned at an angle to the vertical and which each run parallel to one another.
  • Each inclined plate 202 is corrugated, in particular corrugated or ribbed, with the inclined plates 202 being aligned so that the direction of extension of the corrugations, in particular the corrugations or ribs, extend from bottom to top at an angle to the vertical.
  • the process water to be cleaned is introduced through the coalescence separator 201 in such a way that it flows upwards between the inclined plates 202.
  • the inclined plates 202 are designed as lamella plates with a cyclic profile. Drops of liquids with a density less than the density of water collect on the underside of each slat. The drops combine with other drops to form larger drops, which float the lower density of the drops compared to water and collect in the upper area 203 of the coalescence separator 200.
  • the collected liquid can be removed via removal points 204 and transferred to a collection tank 205.
  • the pure water from the coalescence separator 200 is transferred to the pure water tank 300 via a coalescence separator outlet 206.
  • the coalescence separator 200 also has fastening elements 207, via which radiation shielding elements, not shown, are fastened for shielding from ionizing radiation, in particular gamma radiation.
  • the coalescence separator 201 further comprises a collecting container 210, which is funnel-shaped. Coalescing separation is based on relatively low flow velocities, which enable the drops to coalesce. At the same time, however, it is also possible that part of the remaining particle load settles and uncontrolled particle deposits occur in the coalescence separator 201. To prevent this, the collecting container 210 is designed in which the corresponding particles collect. The particles in the collecting container 210 can be removed by backwashing via a backwash line 211 and fed to filtration, for example in the vacuum belt filter 100 or the filter system 400.
  • the filter system 400 includes a first filter 401 and a second filter 402.
  • a filter medium flows through from the inside to the outside, with a filter cake building up inside.
  • the pressure loss across the filter medium is monitored and the interior of the first filter 401 is cleaned when the pressure loss exceeds a predeterminable limit value. This is preferably done mechanically, the removed filter cake is rinsed out with process water and transferred as filter residue 405 to the vacuum belt filter 100 and there applied to the filter cake 116 via the filter residue feeder 117 (cf. Fig. 2 ).
  • the first filter 401 is also referred to as a so-called lensing filter.
  • the second filter 402 is an analysis filter with which the functionality and efficiency of the first filter 401 can be analyzed.
  • the second filter 402 is formed downstream of the first filter 401, so that the pure water purified by the first filter 401 flows through the second filter 402.
  • the second filter 402 is designed in particular as a so-called absolute filter. This refers to a filter that has a precisely defined separation limit. For example, if an absolute filter with a cutoff limit of 1 ⁇ m [micrometers] is used, only particles with a diameter of less than 1 ⁇ m can pass through it.
  • the separation limit of the second filter 402 is chosen so that it corresponds to the filter behavior of the first filter 401, so that in normal operation it reliably filters out particles with a diameter smaller than the separation limit of the second filter 402, so that when particles in the second Filter 402 are filtered out, a malfunction of the first filter 401 can be assumed.
  • the second filter 402 is used as a so-called police filter. If particles are found in the second filter 402, it can be assumed that the elements of the device located upstream of the second filter 402 are malfunctioning.
  • the UV system 500 can be irradiated with UV radiation to inactivate germs.
  • the filtrate or pure water that leaves the filter system 400 is transferred to the pure water tank 300 via a supply line 403.
  • the water can be removed from this again to carry out decoating or to backwash the first filter 401.
  • the device 1 described here as well as the corresponding procedure allows the safe separation of particles up to a particle size of 1 micrometer and the safe separation of oils, fats and the like from the process water, so that the corresponding pure water is supplied again under pressure by a corresponding pump a high-pressure treatment of a coated element can be promoted.
  • the resulting filter residues are free of secondary filters, so that the resulting amount of filter residues can be reduced compared to approaches assumed to be known.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Food Science & Technology (AREA)
  • Physical Water Treatments (AREA)
  • Filtering Materials (AREA)
  • Saccharide Compounds (AREA)

Claims (9)

  1. Procédé de déstratification d'éléments revêtus d'une installation basée sur la technique nucléaire, comprenant un traitement sous haute pression utilisant une eau de traitement, dans lequel l'eau de traitement (10) est soumise à une eau pure (404) en vue de préparer au moins une préparation à deux niveaux, comprenant :
    a) une filtration sous pression dans laquelle une ceinture de filtration poreuse (103) pourvue d'un côté inférieur est guidée au-dessus d'une chambre de filtration à laquelle une sous-pression est appliquée par rapport à la pression régnant au-dessus de la ceinture de filtration, dans laquelle l'eau de traitement est guidée de telle sorte qu'elle entre en contact avec un côté supérieur de la ceinture de filtration opposée au côté inférieur, de sorte que l'eau de traitement (10) est guidée, grâce à la sous-pression appliquée du côté supérieur, au travers de la ceinture de filtration (103) jusqu'à atteindre le côté inférieur de la ceinture de filtration, dans laquelle au moins une partie des matières solides contenues dans l'eau de traitement restent sous forme de gâteau de filtre (106) sur la ceinture de filtration, ledit gâteau étant transféré dans un récipient de collecte (108), dans lequel l'eau de traitement au moins en partie libérée par les matières solides est évacuée sous forme de filtrat ; et
    b) une séparation des hydrocarbures, dans laquelle l'eau de traitement (10) est soumise à une séparation par coalescence (200) en vue de séparer les hydrocarbures.
  2. Procédé selon la revendication 1, dans lequel la ceinture de filtration est déplacée de façon circonférentielle au cours de l'étape a).
  3. Procédé selon l'une quelconque des revendications précédentes, dans lequel au moins un des fluides suivants :
    A) l'eau de traitement (10) ;
    B) le filtrat (113) ; et
    C) l'eau pure (404) ;
    est soumis à une irradiation au rayonnement UV.
  4. Procédé selon l'une quelconque des revendications précédentes, dans lequel au moins un des fluides suivants :
    A) l'eau de traitement (10) ;
    B) le filtrat (113) ; et
    C) l'eau pure (404) ;
    est soumis à au moins une des mesures suivantes :
    i) mesure de l'activité radiologique ;
    ii) mesure de la conductivité électrique ;
    iii) mesure de la charge en particules ; et
    iv) mesure de la distribution en taille des particules.
  5. Procédé selon la revendication 4, dans lequel l'eau pure sert d'eau de traitement permettant de réaliser un traitement sous haute pression lorsque le résultat des mesures réalisées se situent en dessous d'une valeur limite prédéfinissable respective.
  6. Procédé selon la revendication 4 ou 5, dans lequel les paramètres de traitement sont modifiés au moins à une des étapes a) et/ou b) en fonction des résultats d'au moins une des mesures effectuées.
  7. Procédé selon l'une quelconque des revendications précédentes, dans lequel l'eau pure est utilisée pour mettre en œuvre un traitement sous haute pression de déstratification.
  8. Procédé selon l'une quelconque des revendications précédentes, dans lequel à l'étape b) les particules se sédimentant sont reçues dans un récipient de collecte (210) .
  9. Procédé selon la revendication 8, dans lequel les particules présentes dans le récipient de collecte (210) sont retirées dudit récipient au travers d'un processus de lavage à contre-courant.
EP21736546.9A 2020-06-30 2021-06-21 Procédé de décontamination liquide des objets contaminés radioactivement et retraitement d`eau du procédé Active EP4154279B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE102020117227.3A DE102020117227A1 (de) 2020-06-30 2020-06-30 Verfahren zur Nassdekontamination von radioaktiv kontaminierten Werkstücken mit Prozesswasseraufbereitung
PCT/EP2021/066832 WO2022002668A2 (fr) 2020-06-30 2021-06-21 Procédé de décontamination par voie humide de pièces présentant une contamination radioactive avec traitement de l'eau de procédé

Publications (3)

Publication Number Publication Date
EP4154279A2 EP4154279A2 (fr) 2023-03-29
EP4154279B1 true EP4154279B1 (fr) 2023-10-04
EP4154279C0 EP4154279C0 (fr) 2023-10-04

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EP21736546.9A Active EP4154279B1 (fr) 2020-06-30 2021-06-21 Procédé de décontamination liquide des objets contaminés radioactivement et retraitement d`eau du procédé

Country Status (4)

Country Link
EP (1) EP4154279B1 (fr)
DE (1) DE102020117227A1 (fr)
ES (1) ES2967378T3 (fr)
WO (1) WO2022002668A2 (fr)

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3962078A (en) 1974-12-13 1976-06-08 Hydromation Filter Company Method and apparatus for treating liquid contaminated with radioactive particulate solids
JPS55116415A (en) 1979-03-02 1980-09-08 Tokyo Electric Power Co Inc:The Filtration apparatus
US6387274B1 (en) 2000-03-28 2002-05-14 Chem-Nuclear Systems, Llc System and method for the removal of radioactive particulate from liquid waste
US9782694B2 (en) * 2011-03-03 2017-10-10 Siemens Energy, Inc. Composite media for water treatment processes and methods of using same

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Publication number Publication date
WO2022002668A3 (fr) 2022-02-24
ES2967378T3 (es) 2024-04-30
EP4154279C0 (fr) 2023-10-04
DE102020117227A1 (de) 2021-12-30
EP4154279A2 (fr) 2023-03-29
WO2022002668A2 (fr) 2022-01-06

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