EP2302642A1 - Verfahren zur Behandlung von radioaktiven Feststoffen - Google Patents

Verfahren zur Behandlung von radioaktiven Feststoffen Download PDF

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Publication number
EP2302642A1
EP2302642A1 EP10178759A EP10178759A EP2302642A1 EP 2302642 A1 EP2302642 A1 EP 2302642A1 EP 10178759 A EP10178759 A EP 10178759A EP 10178759 A EP10178759 A EP 10178759A EP 2302642 A1 EP2302642 A1 EP 2302642A1
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EP
European Patent Office
Prior art keywords
concrete
self
solid materials
leveling
cavity
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.)
Withdrawn
Application number
EP10178759A
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English (en)
French (fr)
Inventor
Serge Berthouly
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Baltymore
Original Assignee
Baltymore
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Baltymore filed Critical Baltymore
Publication of EP2302642A1 publication Critical patent/EP2302642A1/de
Withdrawn legal-status Critical Current

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    • 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
    • G21F9/301—Processing by fixation in stable solid media
    • G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
    • G21F9/304—Cement or cement-like matrix
    • 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
    • G21F9/34—Disposal of solid waste

Definitions

  • the present invention relates to a method of treating radioactive solid materials.
  • It relates more particularly to a method of treating blocks and / or concrete rubble from the dismantling of buildings exposed to radioactivity and having a mass radioactivity of less than 100 Becquerels per gram (Bq / g).
  • Radioactive materials with a mass radioactivity of less than 100 Bq / g are so-called very low-activity materials or wastes, ie whose activity level is very close to natural radioactivity, with a mass radioactivity generally between 1 and 100 Bq / g sometimes more for very small volumes. A few decades are enough for their level of activity to reach an average level of a few Bq / g, the residual radioactivity being mainly due to long-lived elements.
  • One of the methods disclosed in this document is to mix the special waste in the presence of a hardener with a binder hardening by chemical reaction and which becomes water repellent after the reaction, the resulting mixture being brought to the molten or fluid state immediately in a landfill where it is about to solidify or harden.
  • this process aims at stacking the products of the process above the ground level, and in particular to fill, with the mixture made, the cavities of a discharge already filled with other special waste, namely the spaces separating metal or plastic drums disposed in the landfill and containing special waste.
  • This method therefore aims to trap special waste in solid layers, directly to the air in a landfill, possibly filling the interstitial spaces between the storage drums already present in the landfill, which is completely unsuitable for the treatment of radioactive solid materials.
  • the method disclosed in these documents DE 20 39 130 or US 3,513,100 aims to inject a fluid concrete containing highly radioactive solid waste in wellbore cracks.
  • the fluid concrete used in this process is non-porous, to prevent dispersion of the radioactive particles in the aqueous phase, and contains no emulsifier and contains only a small amount of oil or other additives that could make porous concrete porous .
  • this fluid concrete is probably adapted to at least partially fill the crack, provided to apply a sufficiently high injection pressure.
  • this concrete without emulsifier and containing few additives would be unsuitable to completely fill a large cavity, such as a karst cavity, because of its composition which does not provide a sufficiently high fluidity.
  • the present invention is intended in particular to solve all or part of the disadvantages mentioned above, by proposing a radioactive solid material treatment process that is fast, economical, easy, able to optimize the available storage volume in the underground cavities , for industrial and / or bulk processing of radioactive solid materials.
  • Cementitious self-leveling concrete compositions are generally used for casting and making smooth surface screeds because they have the advantage that the surface of the cast product develops a smooth appearance and a good leveling by its own properties, such as its properties of low colloid and of great fluidity.
  • the fluid self-leveling concrete screeds formed from such compositions thus have a particularly remarkable self-leveling and self-leveling character, including an ability to catch uneven levels without the application of external vibrations and ease of operation resulting from the ability to pump easily. and effectively fresh concrete on great heights.
  • a cementitious composition of self-leveling concrete in the process according to the invention makes it possible to produce a fluid self-leveling concrete screed which will be easily injectable into the subterranean cavity, directly in contact with the walls delimiting this cavity, which will make it possible to fill quickly and optimally the cavity, that is to say without volume unexploited or not filled by the concrete.
  • the fluid screed will spread in substantially horizontal layers catching the differences in levels inherent to a natural underground cavity, knowing that such a karstic underground cavity can have dimensions (height, width) of the order of a few tens of meters to a few hundred meters.
  • This process thus makes it possible to treat large quantities of radioactive materials, industrially or in bulk, while ensuring efficient storage in the underground cavity.
  • the mineral material used by man at the beginning of the cycle to carry out his industrial activities returns to his mineral and final condition; the aggregates converted into concrete are then recycled in a sustainable manner.
  • the principle of recycling that governs this process ensures that the aggregates that originally allowed the manufacture of concrete, return to their original form by joining the subsoil. In the end, the material will enter a slow cycle of natural reduction of its radiant activity without worry or risk for human activity.
  • the radioactive solid materials consist of blocks and / or concrete rubble from the dismantling of buildings exposed to radioactivity.
  • the concrete blocks and / or rubble are armed with a steel structure, said method comprising a preliminary deconstruction step of demolishing buildings to form concrete blocks or rubble and then separating the blocks and / or concrete rubble of the steel structure.
  • the solid materials constitute materials whose mass radioactivity is less than 100 Becquerels per gram.
  • Such materials, whose activity level is very close to the natural radioactivity, are particularly suitable for the process according to the invention because the injection of the fluid screed is directly in contact with the walls of an underground cavity, without coating or additional container.
  • the method comprises, after the crushing step T1), a step of transporting the crushed solid materials to the burial site, by means of containers provided with radiation isolation means.
  • the injection step T3) consists in injecting the self-leveling fluid concrete screed into an underground cavity via a plurality of injection wells spaced apart from one another.
  • the method comprises a preliminary drilling step of drilling one or more injection wells at the burial site distributed along a predetermined drilling plane.
  • the method comprises a final step of closing the injection well (s) by filling over a predetermined height with a sealing material, in particular sand.
  • the step T3) consists in injecting the self-leveling concrete fluid screed discontinuously, in successive layers until the at least partial filling of the underground cavity.
  • the method comprises, after the crushing step T1), a step of screening the crushed solid materials in several granulometric cuts, in particular cuts having a particle size of between 0 and 4 mm and / or between 4 and 10 mm. and / or between 10 and 20 mm.
  • This method is particularly adapted to be implemented with an underground cavity of karstic type and / or which has dimensions, in height and / or in width, of the order of a few tens of meters to a few hundred meters.
  • the invention relates to a method for treating radioactive solid materials of very low activity, that is to say having a mass radioactivity of between 1 and 100 Bq / g (100 Becquerels per gram).
  • This method applies more particularly to concrete blocks and / or rubble 1 armed with a steel structure 2, from the dismantling of buildings B exposed to radioactivity.
  • Such blocks or concrete rubble generally have a particle size or blockometry of between 0 and 500 mm after demolition of the building.
  • This method also applies to concrete (not shown) concrete costs derived from the milling of concrete blocks or walls over a given thickness, for example of the order of 3 to 10 mm, in order to eliminate surface radioactive pollution. .
  • Such mills generally have a particle size of between 0 and 10 mm, or even between 0 and 20 mm.
  • the latter is carried out by means of deconstruction equipment provided with specific protection means against radiation.
  • This hydraulic excavator is for example able to ensure the demolition of walls, wall or floor type, and the beams of building B, reinforced concrete in a block size between 0 and 500 mm.
  • the tool holder of the shovel can also carry, via a hydraulic quick coupler, a hydraulic shear to cut the steel elements (scrap type or metal reinforcement) and concrete elements (beam or wall type) and achieve the optimum blockometry for the next crushing step, namely between 0 and 500 mm.
  • the excavator's tool holder can also carry a bucket and a hydraulic grapple via a hydraulic quick coupler.
  • the various hydraulic attachments of the various tools have the advantage, in addition to saving time of replacement, to avoid any unprotected human intervention. radiation; the driver of the shovel can, from his cabin under confinement, change tool at will without being exposed.
  • a mobile wheel loader takes the materials concrete / steel blockometry between 0 and 500 mm to feed the crushing means described below.
  • This loader like the shovel or the excavator, has a system of treatment and filtration of the air, as well as a system of dosimetric control of the level of radioactivity.
  • the dosimetric control systems installed respectively on the excavator or the excavator and on the loader can be connected to a central safety cell located on the deconstruction site, in order to teletransmit and record the radioactivity data to maintain a traceability of the risk. .
  • the collection of radioactivity data and other safety information is generalized in all other stages of the treatment process, both at the deconstruction site and at the landfill site.
  • the latter is done in two stages with a first crushing, said primary crushing, and a second crushing, said secondary crushing.
  • the first crushing device is advantageously remotely controlled by the driver of the loader described above; the latter can for example, from his cabin, modulate the feed rate of the first crushing device.
  • the screening step of the crushed materials, coming from the second crushing device, in several granulometric cuts is carried out by means of a screening device fed with crushed materials having a particle size of between 0 and 20 mm.
  • the cuts having a particle size greater than 20 mm are recycled in the second crushing device in order to undergo the secondary crushing step again.
  • the aggregates 10, 11, 12 or materials resulting from the screening step are then stored in respective silos, for example metal silos, before being loaded into the respective transport containers 3 used in the next step of transport.
  • Each container 3 corresponds to aggregates in a given cut, for example in the first or second or third cut.
  • the step of transporting the aggregates 10, 11, 12, resulting from the various steps mentioned above carried out on the deconstruction site, to the landfill site is carried out by means of the specific containers 3 visible on the figures 1 and 2 .
  • the discharge of aggregates 10, 11, 12 to the landfill is effected for example mainly by rail.
  • the containers 3 can arrive by train if a rail junction is possible, otherwise they will be transhipped on trailer seedlings 7 equipped with container carrier 70 for the final journey, as illustrated in FIG. figure 2 .
  • the containers 3 are provided with sealing means and are fully enclosed to achieve the desired seal. It is also envisaged to carry out this transport with sealed trailer seedlings.
  • the containers 3 are sized to contain for example about 20 tons of aggregates; this payload capacity being compatible with the legislation for loading on trailer seedlings 7 equipped with container ships 70.
  • the containers 3 have in the upper part 30 hatches 32 allowing loading under hopper by means of a flexible handle, for example with a diameter of 300 mm.
  • traps 32 for example three in number, are circular in shape and allow sufficient gravity filling containers.
  • the upper portion 30 has a double slope roof shape to optimize the gravity loading per sleeve to complete the 20 tons planned.
  • the rear door 31 and the hatches 32 are provided with sealing means and appropriate closure to prevent any loss of materials during transport.
  • the container holder 70 has a rear hinge 71 and a front ram 72 for unloading materials 10, 11, 12 transported in a receiving hopper 73 on the landfill site.
  • the receiving hopper 73 opens onto a conveyor line 74, for example of the conveyor belt line type, which leads the materials into corresponding storage silos.
  • the materials are thus stored in three granulometric cuts 10, 11, 12 in three silo batteries.
  • weight control means or weight control means, which will be used for a pre-dosing of the materials according to their grain size cuts; this pre-dosing being necessary for the next mixing step.
  • the mixing step consisting in producing a self-leveling fluid concrete screed 5 and partly diagrammed on the figure 3 , the latter is carried out essentially in a concrete plant 8, provided with a mixer 80.
  • the concrete plant 8 is supplied with materials 10, 11, 12 crushed and screened via the respective extractors.
  • the concrete plant 8 is supplied with cementitious self-leveling concrete composition 4 via one or more conveying lines fed with cement and admixtures, not counting water.
  • the concrete plant 8 is thus equipped with two or more cement silos, as well as additional tanks and / or silos for the storage of the adjuvants.
  • the mixing step is for example controlled by computer control means controlling the feeds of aggregates, cement, admixtures and water, as well as speed and mixing times.
  • the entire concrete plant 8 is confined in a building that is impervious to water and air, in particular by means of a filtering depressurization device.
  • the latter is carried out essentially using a drill, including the type "bottom hole” hammer whose standard diameter is for example six inches and equipped with eight-inch cutters.
  • the depth of the injection wells 6 is adapted to the depth of the cavities C in a range of 40 to 500 m.
  • the injection wells 6 will, if necessary, be jacketed with tubes sealing the well, such as for example thermoplastic polymer tubes, such as polyvinyl chloride or high density polyethylene, or steel tubes.
  • tubes sealing the well such as for example thermoplastic polymer tubes, such as polyvinyl chloride or high density polyethylene, or steel tubes.
  • the injection wells 6 are spaced from each other and distributed along a predetermined drilling plane, such as a mesh of predefined width L, in particular of the order of 40 m. This means that the drilling will take place on an area where the injection and 6 injection are spaced from each other at least a distance L of 40 meters.
  • the latter is carried out essentially by means of pipes 90 and one or more concrete pumps for circulating the fluid screed 5 in the pipes 90.
  • this fluid screed 5 will thus be conveyed from the concrete batching plant 8 to the injection well 6 via the pipes 90 and by a pump, in particular of the concrete pump type.
  • Relay pumps may be required depending on the length of the pipes 90 and the extent of the landfill.
  • the heads 60 of the injection wells 6 are closed and covered by valve and shutter devices mounted on the pipes 90.
  • the fluid screed 5 is injected at low pressure into the injection wells 6.
  • the fluid screed 5 is layered up to about 20 m from the axes of the injection wells 6.
  • the cavity C is thus filled progressively in successive layers until the total filling of the cavity C.
  • the injection of the fluid screed 5 can be made either continuously or discontinuously.
  • the self-leveling concrete thus cast and solidified has very low propensities for weathering over time.
  • the last step of closing the injection wells 6 is performed when the cavity C is full, the injection wells 6 being plugged or condemned by filling with sand over a height H, for example at least 30 meters.
  • the heads 60 of the injection wells 6 are then sealed after having been fitted with sheaths that may, for example, house sensors for controlling the radiating activity in order to follow the decay in the time of the radioactivity.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Environmental & Geological Engineering (AREA)
  • Processing Of Solid Wastes (AREA)
EP10178759A 2009-09-23 2010-09-23 Verfahren zur Behandlung von radioaktiven Feststoffen Withdrawn EP2302642A1 (de)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR0956546A FR2950467B1 (fr) 2009-09-23 2009-09-23 Procede de traitement de materiaux solides radioactifs

Publications (1)

Publication Number Publication Date
EP2302642A1 true EP2302642A1 (de) 2011-03-30

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Application Number Title Priority Date Filing Date
EP10178759A Withdrawn EP2302642A1 (de) 2009-09-23 2010-09-23 Verfahren zur Behandlung von radioaktiven Feststoffen

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EP (1) EP2302642A1 (de)
FR (1) FR2950467B1 (de)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107812781A (zh) * 2017-12-07 2018-03-20 河南核净洁净技术有限公司 一种对低放射性密褶型废过滤器进行拆解的设备及其方法
WO2019037958A1 (fr) * 2017-08-22 2019-02-28 Agence Nationale Pour La Gestion Des Dechets Radioactifs Procédé et installation de bétonnage d'un site souterrain

Citations (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3513100A (en) 1967-09-25 1970-05-19 Halliburton Co Method for subsurface disposal of radioactive waste
DE2039130A1 (de) 1970-08-06 1972-02-10 Halliburton Co Verfahren zum Beseitigen von zerkleinerten,festen,radioaktiven Abfallstoffen
FR2516292A1 (fr) 1981-11-10 1983-05-13 Stockage Assainissement Coulis special d'injection et son utilisation pour le stockage dans le sol de dechets radioactifs
US4432666A (en) 1979-12-14 1984-02-21 Vfi, Verwertungsgesellschaft Fur Industrieruckstande Mbh Process for the storage and dumping of waste materials
FR2624410A1 (fr) 1987-12-11 1989-06-16 Geostock Procede de confinement souterrain de dechets dans une cavite creusee par lessivage dans le sel
DE4023117A1 (de) 1990-07-20 1992-01-30 Kernforschungsz Karlsruhe Verfahren zum endlagern von schwach kontaminiertem bauschutt aus dem abriss kerntechnischer anlagen und vorrichtung zur durchfuehrung des verfahrens
DE4023118A1 (de) 1990-07-20 1992-01-30 Kernforschungsz Karlsruhe Verfahren zum endlagern von schwach kontaminiertem bauschutt aus dem abriss kerntechnischer anlagen und vorrichtung zur durchfuehrung des verfahrens
FR2704853A1 (fr) 1993-05-07 1994-11-10 Dijon Beton Béton à propriété autolissante et autonivelante.
WO1996020901A1 (fr) 1994-12-30 1996-07-11 Rhone-Poulenc Chimie Mortier fluide autonivelant comprenant du sulfate de calcium et de la chaux
FR2751956A1 (fr) 1996-07-30 1998-02-06 Grp Francais De Construction G Composition de beton de structure autonivelant et autolissant
WO1998051637A1 (fr) 1997-05-12 1998-11-19 Lafarge S.A. Composition autonivelante a base de ciment
EP0724271B1 (de) 1994-12-22 1999-04-07 R.T.C. Realisations Techniques Et Commerciales Verfahren und Vorrichtung zur Behandlung radioaktiver Abfälle durch hydraulisches Bindemittel
WO1999025664A1 (fr) 1997-11-17 1999-05-27 Vicat Agent modificateur d'hydratation pour mortier ou beton a retrait limite
EP0934915A1 (de) 1998-02-06 1999-08-11 Entreprise Quillery & Cie Selbstnivellierender sehr hoher Leistungsbeton, Verfahren zu seiner Herstellung und seine Verwendung
WO2000066512A1 (fr) 1999-05-04 2000-11-09 Electricite De France (Service National) Beton pour la construction de chapes auto-nivelantes et son procede d'utilisation
FR2815342A1 (fr) 2000-10-13 2002-04-19 Francais Ciments Composition cimentaire, son utilisation pour la realisation de chape liquide autonivelante et chape ainsi obtenue
EP1683768A1 (de) 2004-12-27 2006-07-26 Ciments Francais Zementzusammensetzung enthaltend ein Antischrumpfmittel und seine Verwendung für die Herstellung von flüssigen Estrichen
FR2919602A1 (fr) 2007-07-30 2009-02-06 Francais Ciments "melange d'adjuvants modificateurs de rheologie pour beton autoplacant et beton autoplacant renfermant un tel melange"

Patent Citations (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3513100A (en) 1967-09-25 1970-05-19 Halliburton Co Method for subsurface disposal of radioactive waste
DE2039130A1 (de) 1970-08-06 1972-02-10 Halliburton Co Verfahren zum Beseitigen von zerkleinerten,festen,radioaktiven Abfallstoffen
US4432666A (en) 1979-12-14 1984-02-21 Vfi, Verwertungsgesellschaft Fur Industrieruckstande Mbh Process for the storage and dumping of waste materials
FR2516292A1 (fr) 1981-11-10 1983-05-13 Stockage Assainissement Coulis special d'injection et son utilisation pour le stockage dans le sol de dechets radioactifs
FR2624410A1 (fr) 1987-12-11 1989-06-16 Geostock Procede de confinement souterrain de dechets dans une cavite creusee par lessivage dans le sel
DE4023117A1 (de) 1990-07-20 1992-01-30 Kernforschungsz Karlsruhe Verfahren zum endlagern von schwach kontaminiertem bauschutt aus dem abriss kerntechnischer anlagen und vorrichtung zur durchfuehrung des verfahrens
DE4023118A1 (de) 1990-07-20 1992-01-30 Kernforschungsz Karlsruhe Verfahren zum endlagern von schwach kontaminiertem bauschutt aus dem abriss kerntechnischer anlagen und vorrichtung zur durchfuehrung des verfahrens
FR2704853A1 (fr) 1993-05-07 1994-11-10 Dijon Beton Béton à propriété autolissante et autonivelante.
EP0724271B1 (de) 1994-12-22 1999-04-07 R.T.C. Realisations Techniques Et Commerciales Verfahren und Vorrichtung zur Behandlung radioaktiver Abfälle durch hydraulisches Bindemittel
WO1996020901A1 (fr) 1994-12-30 1996-07-11 Rhone-Poulenc Chimie Mortier fluide autonivelant comprenant du sulfate de calcium et de la chaux
FR2751956A1 (fr) 1996-07-30 1998-02-06 Grp Francais De Construction G Composition de beton de structure autonivelant et autolissant
WO1998051637A1 (fr) 1997-05-12 1998-11-19 Lafarge S.A. Composition autonivelante a base de ciment
WO1999025664A1 (fr) 1997-11-17 1999-05-27 Vicat Agent modificateur d'hydratation pour mortier ou beton a retrait limite
EP0934915A1 (de) 1998-02-06 1999-08-11 Entreprise Quillery & Cie Selbstnivellierender sehr hoher Leistungsbeton, Verfahren zu seiner Herstellung und seine Verwendung
WO2000066512A1 (fr) 1999-05-04 2000-11-09 Electricite De France (Service National) Beton pour la construction de chapes auto-nivelantes et son procede d'utilisation
FR2815342A1 (fr) 2000-10-13 2002-04-19 Francais Ciments Composition cimentaire, son utilisation pour la realisation de chape liquide autonivelante et chape ainsi obtenue
EP1683768A1 (de) 2004-12-27 2006-07-26 Ciments Francais Zementzusammensetzung enthaltend ein Antischrumpfmittel und seine Verwendung für die Herstellung von flüssigen Estrichen
FR2919602A1 (fr) 2007-07-30 2009-02-06 Francais Ciments "melange d'adjuvants modificateurs de rheologie pour beton autoplacant et beton autoplacant renfermant un tel melange"

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2019037958A1 (fr) * 2017-08-22 2019-02-28 Agence Nationale Pour La Gestion Des Dechets Radioactifs Procédé et installation de bétonnage d'un site souterrain
FR3070416A1 (fr) * 2017-08-22 2019-03-01 Agence Nationale Pour La Gestion Des Dechets Radioactifs Procede et installation de betonnage d’un site souterrain
CN110998031A (zh) * 2017-08-22 2020-04-10 国家放射性废物管理局 用于对地下位置进行混凝土浇注的方法和设施
CN110998031B (zh) * 2017-08-22 2021-12-10 国家放射性废物管理局 用于对地下位置进行混凝土浇注的方法和设施
CN107812781A (zh) * 2017-12-07 2018-03-20 河南核净洁净技术有限公司 一种对低放射性密褶型废过滤器进行拆解的设备及其方法
CN107812781B (zh) * 2017-12-07 2023-09-12 河南核净洁净技术有限公司 一种对低放射性密褶型废过滤器进行拆解的设备及其方法

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Publication number Publication date
FR2950467A1 (fr) 2011-03-25
FR2950467B1 (fr) 2011-10-28

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