WO2011098817A1 - Appareil et procédé de mélange - Google Patents

Appareil et procédé de mélange Download PDF

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Publication number
WO2011098817A1
WO2011098817A1 PCT/GB2011/050245 GB2011050245W WO2011098817A1 WO 2011098817 A1 WO2011098817 A1 WO 2011098817A1 GB 2011050245 W GB2011050245 W GB 2011050245W WO 2011098817 A1 WO2011098817 A1 WO 2011098817A1
Authority
WO
WIPO (PCT)
Prior art keywords
container
projecting elements
housing
cylindrical
agitation
Prior art date
Application number
PCT/GB2011/050245
Other languages
English (en)
Inventor
John Neil Clifford
Rodney Smith
David Tyson
Original Assignee
Nuclear Decommissioning Authority
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 Nuclear Decommissioning Authority filed Critical Nuclear Decommissioning Authority
Publication of WO2011098817A1 publication Critical patent/WO2011098817A1/fr

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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
    • G21F9/28—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
    • C—CHEMISTRY; METALLURGY
    • C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B18/00—Use of agglomerated or waste materials or refuse as fillers for mortars, concrete or artificial stone; Treatment of agglomerated or waste materials or refuse, specially adapted to enhance their filling properties in mortars, concrete or artificial stone
    • C04B18/04—Waste materials; Refuse
    • C04B18/0463—Hazardous waste
    • C—CHEMISTRY; METALLURGY
    • C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B26/00—Compositions of mortars, concrete or artificial stone, containing only organic binders, e.g. polymer or resin concrete
    • C04B26/02—Macromolecular compounds
    • C04B26/26—Bituminous materials, e.g. tar, pitch
    • C—CHEMISTRY; METALLURGY
    • C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B28/00—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
    • C04B28/02—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
    • 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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/16—Processing by fixation in stable solid media
    • G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
    • G21F9/165—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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/16—Processing by fixation in stable solid media
    • G21F9/167—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
    • C—CHEMISTRY; METALLURGY
    • C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
    • C04B2111/00474—Uses not provided for elsewhere in C04B2111/00
    • C04B2111/00767—Uses not provided for elsewhere in C04B2111/00 for waste stabilisation purposes
    • C04B2111/00784—Uses not provided for elsewhere in C04B2111/00 for waste stabilisation purposes for disposal only
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies
    • Y02W30/91—Use of waste materials as fillers for mortars or concrete

Definitions

  • This invention relates to a mixing apparatus and method of mixing which finds particular, but not exclusive, use in the processing and storage of radioactive waste.
  • radioactive waste materials such as, for example, materials from nuclear reactor piles
  • processing may typically include the steps of encapsulating the waste material in a hardenable material such as concrete, allowing the hardenable material to harden in a container, and subsequently sealing and storing the container.
  • US-A-4666676 discloses an apparatus for processing and storing liquid radioactive materials wherein a cement slurry is fed into a mixing container, and the liquid radioactive material is metered into the container.
  • the contents of the container are mixed using a rotatable blade, which typically rotates at about 100 rpm and can be inserted into and removed from the container via an opening in the top of the container.
  • the container is substantially sealed. After mixing, the container is removed from the apparatus, and the mixed contents of the container are allowed to solidify.
  • US-A-4379081 teaches a method of encapsulating liquid radioactive waste wherein the waste is mixed with a cement slurry to form a hydraulic cement thixotropic paste with extreme mouldability which will not bleed, and which sets more rapidly than mixtures subjected to normal mixing processes in order to form a very strong product.
  • the mixing process occurs at a very high shear rate using a so-called "colloidal" mixer having a rotatable mixing disc in a housing, the mixing occurring in a gap of less than about 3 mm between the mixing disc and the housing. In operation, the mixing disc is rotated at about 2000 rpm.
  • US-A-4234447 is concerned with a method and apparatus for storing aqueous radioactive waste, wherein the waste is mixed with a hardenable resin in a storage drum. An agitator is then inserted into the storage drum via an opening in the top of the drum and, after mixing, the agitator is removed and the drum contents are allowed to harden.
  • IAEA Report 402 International Atomic Energy Agency, "Handling and Processing of Radioactive Waste from Nuclear Applications", Technical Reports Series No. 402, IAEA, Vienna, 2001 ] discloses various processes for immobilising radioactive waste, and includes discussions of suitable matrix materials, mixing processes and the sizes and types of containers which are required for storing the immobilised radioactive waste. For cementation processes, it is suggested to use either a re-usable mixing paddle or a disposable mixing paddle.
  • a re-usable mixing paddle is one which is used to stir the contents of the container and is removed before the container is capped and the mixture is allowed to set.
  • a disadvantage of using a re-usable paddle is that the residue on the mixing paddle must be removed, and the paddle washed, in order to prevent area and container contamination.
  • a disposable mixing paddle is used to stir the contents of the container, and is then left in the container. This technique is referred to as the "lost paddle" approach and involves the use of a paddle that is inexpensive to fabricate but capable of producing a homogeneous mix.
  • IAEA Report 402 also discloses that cement and bitumenisation processes have been used extensively for immobilising radioactive waste.
  • corresponding polymer processes have only been used to a limited extent for the immobilisation of radioactive waste, and mainly in the context of ion exchange resins.
  • thermoplastic and thermosetting polymers have been used for this purpose.
  • uranium metal corrodes when in contact with air, some other common gases and water. This corrosion most often involves reactions of the uranium metal with oxygen (gaseous or dissolved) and water (liquid or vapour), which may be present as bound water in an encapsulant/waste mixture used for the immoblisation of radioactive wastes containing uranium.
  • oxygen gaseous or dissolved
  • water liquid or vapour
  • One topic that has generated considerable interest over the years is the generation of uranium hydride during the corrosion of uranium metal in certain environments. This has been of concern primarily because uranium hydride is pyrophoric in some forms under certain conditions.
  • uranium metal In most environments encountered in practice, the corrosion of uranium metal involves its reaction with either, or both, oxygen and water.
  • oxygen can be present as a gas (e.g. uranium metal in air) or in solution (e.g. uranium metal immersed in water).
  • water may be present as a liquid (e.g. uranium metal immersed in water) or as a vapour (e.g. uranium metal in air or another gas).
  • the reactions of uranium metal with oxygen and water can be represented by the following equations: U (s) + 0 2 (g)/(aq) ⁇ U0 2 ( s ) (1 )
  • 's' represents the solid phase
  • ' ⁇ represents the liquid phase
  • 'g' represents the gas phase
  • 'aq' indicate the presence of water.
  • uranium hydride can be generated when uranium metal corrodes in the presence of water and the absence of oxygen in those cases where the hydrogen produced during the corrosion is not free to escape. It is precisely this sort of environment that is of concern to the present inventors. In some circumstances, it is clearly apparent that such an environment is present. Thus, for example, uranium metal sealed in a gas-tight container filled with a damp, oxygen-free gas self-evidently provides such an environment.
  • a case study [Wood, 1994] involved the storage of unirradiated uranium metal rods clad in iron, but having the ends cut (resulting in exposure of the uranium metal), in air-filled steel drums with clamped lids sealed by rubber gaskets.
  • the drums also contained cardboard, plywood and pine. After storage for several years some of the drums were opened.
  • the lid of one of the drums was found to be tightly stuck and considerable force was required to dislodge it. When the lid was loosened, a vigorous reaction occurred inside the drum and the contents caught fire. The lid on the drum was then replaced. Subsequently, the gas inside the drum was sampled and found to contain only nitrogen and a considerable amount of hydrogen.
  • the present invention seeks to alleviate, at least partially, some, any or all of the difficulties associated with the encapsulation of uranium-containing materials and, in particular, to facilitate the safe and efficient encapsulation of these materials in various media by ensuring the availability of oxygen for an indefinite period during buffer storage prior to encapsulation, and during the mixing process, thereby minimizing or avoiding the formation of uranium hydride.
  • an apparatus for the encapsulation of waste materials comprising:
  • said agitation means is rotatably mounted about an axis of rotation in said container and said plurality of aeration means is located on said agitation means.
  • said container comprises a substantially cylindrical container incorporating a base.
  • an inner surface of the cylindrical walls of said container additionally comprises a plurality of aeration means.
  • said agitation means is comprised in a substantially cylindrical housing of smaller diameter than said cylindrical container and the lower end of said cylindrical housing is seated on the base of said cylindrical container.
  • said cylindrical housing comprises a plurality of aeration means, preferably located on at least one of an inner and outer surface of said cylindrical housing.
  • the upper end of said cylindrical housing comprises a housing cover, adapted to fit around said agitation means.
  • said agitation means comprises a lost paddle system.
  • said agitation means comprises a central drive shaft located within a cylindrical sleeve.
  • said agitation means is powered by drive means, located externally to said container.
  • Said drive means may be located above said container but, most preferably, said drive means is located under the base of said container.
  • said plurality of aeration means comprises a plurality of projecting elements which, in the most preferred embodiments of the invention, are located on an inner surface of said cylindrical container, inner and outer surfaces of said cylindrical housing, and an outer surface of said cylindrical sleeve.
  • said projecting elements comprise annular louvers.
  • a mixing system including a plurality of mixing apparatus according to the first aspect of the invention.
  • each said mixing apparatus comprises an agitation device, and the system further including driving means, operable to couple with each agitation device in order to rotate the agitation device and mix the contents of the container.
  • a method for the encapsulation of at least one first component comprising:
  • said at least one second component comprises at least one encapsulant.
  • said method comprises the additional step of agitating said mixture in said apparatus between steps (b) and (c), prior to curing said mixture.
  • said at least one first component comprises at least one waste material.
  • said at least one waste material comprises at least one radioactive waste material, typically comprising uranium and/or its compounds.
  • said waste materials comprise waste materials which are generated in the nuclear industry.
  • Said at least one component may be in solid or liquid form.
  • said waste materials are in solid form and comprise anything from solid powders to large pieces of debris.
  • submicron powders such as graphite powder and uranium fuel rods may both be successfully encapsulated according to the method of the invention, either alone or in mixtures of various ratios.
  • Typical fuel rods or pieces of broken fuel may, for example, have dimensions indicatively 30 cm (1 foot) or more in length.
  • Encapsulation of said first components may be performed using any suitable encapsulant but, typically, this may be selected from hardenable materials including, but not limited to, cementitious materials, bituminous materials and, more preferably, polymeric materials, such as epoxy resins, polyesters, cyanate esters and organic and inorganic silicon- containing polymers.
  • the encapsulant is in liquid form.
  • Figure 1 is a side elevation of an apparatus according to a first aspect of the invention.
  • Figure 2 is an illustration of an arrangement of projecting elements.
  • the apparatus comprises a container and an agitation device, rotatable with respect to the container about an axis of rotation, the agitation device comprising a cylindrical sleeve and projecting elements located on said sleeve, each projecting element projecting outwardly away from the axis of rotation and extending around substantially the full circumference of the sleeve, the projecting elements being arrayed on the sleeve in a series extending parallel to the axis of rotation, with a gap formed between adjacent projecting elements in the series.
  • the projecting elements each present a downwardly angled upper surface, so that, when material enters the container under gravity, the projecting elements preferentially divert the material externally of the sleeve in the container.
  • Said projecting elements are preferably annular louvers.
  • the container has a base and the agitation device is rotatably mounted and couplable with a drive means through the base of the container.
  • said drive means may further include rotational resistance sensing means, operable to reverse the driving rotation direction when the rotational resistance sensing means senses a resistance to rotation above a threshold level.
  • the apparatus according to the first aspect of the invention comprises agitation means in the form of a lost paddle, adapted to remain in the container, and to be sealed in the container with mixed contents of the container.
  • the apparatus according to the invention preferably further includes a sealable vessel adapted to receive and store the container.
  • the container comprises projecting elements projecting inwardly from an internal wall of the container towards the axis of rotation, the container projecting elements extending around substantially the full circumference of the internal wall of the container, the container projecting elements being arrayed on the internal wall of the container in a series extending parallel to the axis of rotation, with a gap formed between adjacent container projecting elements in the series.
  • the apparatus according to the invention additionally comprises a substantially cylindrical housing having an internal surface and an external surface, substantially coaxial with the axis of rotation and located in a space between the cylindrical sleeve of the agitation means and the internal wall of the container, wherein first intermediate projecting elements extend around substantially the full circumference of the internal wall of the housing, the first intermediate projecting elements being arrayed on the internal wall of the housing in a series extending parallel to the axis of rotation, with a gap formed between adjacent projecting elements in the series.
  • said first intermediate projecting elements face the projecting elements held on the cylindrical sleeve.
  • said apparatus preferably includes second intermediate carrier projecting elements extending around substantially the full circumference of the external wall of said housing, said second intermediate carrier projecting elements being arrayed on the external wall of the housing in a series extending parallel to the axis of rotation, with a gap formed between adjacent projecting elements in the series.
  • said second intermediate projecting elements face the container projecting elements projecting inwardly from the internal wall of the container.
  • the gaps between said first and second intermediate projecting elements are able to communicate with each other via at least one opening in the housing, thereby allowing at least some of the contents of the container, during mixing, to pass through said at least one opening in the housing.
  • said housing is connected to the cylindrical sleeve, and is rotatable with said sleeve, so as to form part of the agitation device.
  • an opening is formed in the apparatus according to the invention, between the sleeve and the housing, in order to facilitate the insertion of components which are to be mixed in the container.
  • the method according to the third aspect of the invention essentially comprises mixing at least one first component with at least one second component, which comprises at least one encapsulant, in the mixing apparatus according to the first aspect of the invention, in order to at least partially encapsulate said first component(s) with said encapsulant(s), said method including locating the first component(s) and encapsulant(s) in the mixing apparatus container and agitating the contents of the container by rotating the agitation device in the container.
  • the series of projecting elements comprised in the apparatus of the first aspect of the invention in use, provides an aeration channel for the contents of the container.
  • said at least one first component includes radioactive material, typically radioactive waste material from a nuclear reactor.
  • Said radioactive waste material generally includes uranium oxide and may also further include, unseparated from the uranium oxide ash, at least partially intact fuel rods.
  • Said radioactive waste material may optionally further include, unseparated from the uranium oxide ash, at least partially intact fuel canisters.
  • the agitation device after mixing the first component(s) and encapsulant(s), the agitation device remains in the container and the container is sealed in a sealable vessel, so that said agitation device comprises a so-called "lost paddle”.
  • the apparatus comprises a cylindrical container which incorporates a mixing mechanism which ensures entrainment of encapsulant - which, in preferred embodiments, comprises an organic polymer - into the ash.
  • the cylindrical container is provided with an arrangement of internal louvers, stacked vertically, which act as a lost paddle system for homogenisation during the encapsulation process. Aeration is achieved through the arrangement of louvers (as part of the lost paddle system, referred to as air cells) penetrating the depth of ash material.
  • the louvers create air cells and allow for the supply of air to the uranium debris material loaded into the liner whilst in buffer storage prior to encapsulation. This is intended to aerate the material and prevent the formation of pyrophoric uranium hydride (which can form in anaerobic conditions).
  • each air cell allows for a geometry (ensuring effective ash depth of no greater than 70 mm, with the majority of the ash depth within the container actually being less than 50 mm), which has been demonstrated not to propagate uranium hydride formation.
  • the specified ash depth can be maintained during buffer storage, thereby ensuring ample aeration and providing an adequate heat sink to the ash, thus preventing the propagation of pyrophoric uranium hydroxide.
  • buffer storage can continue for a matter of some years. Indeed, it is envisaged that the waste could be stored almost indefinitely in safety since, as a consequence of the effective aeration, encapsulation can be deferred for a far longer period. It is also found that, during agitation, the use of a lost paddle system prevents jamming from occurring.
  • the container has an outer cylindrical wall 10 which is fixed to base 12.
  • Base 12 has a centrally-located opening (not shown) for the insertion of a drive shaft 14.
  • Drive shaft 14 drives a cylindrical rotatable sleeve 16 which rotates with respect to the base 12.
  • the sleeve 16 forms a seal with the base and waste is prevented from exiting the container at the central opening in the base 12.
  • the sleeve 16 has a stack of louvers 18 extending outwardly.
  • the louvers are each projecting elements providing substantially frusto-conical upper and lower surfaces.
  • Each louver 18 slopes downwardly from the central sleeve.
  • louvers There is a gap between adjacent louvers, the width of each gap being substantially uniform around the sleeve and regularly spaced along the sleeve, so that the louvers are parallel and regularly spaced along the support.
  • Said louvers are solid and smooth, i.e. there are no holes through the louvers and they do not have rough surfaces.
  • the central sleeve 16 is fixed to cylindrical housing 20.
  • the cylindrical housing is rotatable with respect to base 12. Thus, when the central support rotates, the cylindrical housing 20 also rotates.
  • the annular space formed between the support 16 and housing 20 resembles a toroid and thereby acts to create air cells.
  • Cylindrical housing 20 has an inner cylindrical surface and an outer cylindrical surface. Louvers 22 project inwardly from the inner cylindrical surface, whilst louvers 24 project outwardly from the outer cylindrical surface.
  • the cylindrical housing 20 includes openings allowing material to pass between the louvers, from inside the cylindrical housing 20 to outside the cylindrical housing 20.
  • the outer cylindrical wall 10 has an inner cylindrical surface. Louvers 26 project inwardly from the inner cylindrical surface.
  • Housing cover 28 Extending from the central sleeve 16 to the cylindrical housing 20 is a housing cover 28.
  • Housing cover 28 includes an annular opening, allowing material to be gravity-fed into the annular space between louvers 18 and louvers 22.
  • the central sleeve 16 In operation, the central sleeve 16 is rotated. This causes the louvers 18, 22, 24 to rotate at the same angular velocity, whilst functioning as a lost paddle arrangement.
  • the central sleeve is not reciprocated, i.e. there is no up-and-down movement of the central sleeve.
  • louvers prevent debris material from entering the air cells (and thereby generating an air column), these regions fill with encapsulant during the encapsulation process, thereby vastly increasing the surface area of the solid material available to polymer penetration during the mixing process.
  • the circular louvers provide no jamming points for larger solid items, movement of these materials within the liner during paddle actuation serve to create further turbulence forces. All of these effects allow for adequate mixing at low rotational paddle speeds.
  • louvers 18 on the central cylindrical rotatable sleeve 16 located around drive shaft 14 is shown in greater detail in Figure 2.
  • the apparatus comprises a smart drive unit that is capable of monitoring the torque of the lost paddle system.
  • a smart drive unit that is capable of monitoring the torque of the lost paddle system.

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  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Ceramic Engineering (AREA)
  • Structural Engineering (AREA)
  • Materials Engineering (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Chemistry (AREA)
  • Civil Engineering (AREA)
  • Environmental & Geological Engineering (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Mixers Of The Rotary Stirring Type (AREA)

Abstract

L'invention porte sur un appareil pour l'encapsulation de matériaux de déchets, lequel appareil comprend : (a) un récipient ; (b) une pluralité de moyens pour l'aération des matériaux de déchets ; et (c) des moyens d'agitation, lesquels moyens d'agitation sont montés de façon à pouvoir tourner autour d'un axe de rotation dans le récipient, et la pluralité de moyens d'aération est disposée sur les moyens d'agitation. De préférence, les moyens d'agitation comprennent un système à palette perdue, et la pluralité de moyens d'aération comprennent une pluralité d'éléments de projection, ces éléments comprenant de la façon la plus préférable des grilles d'aération annulaires. L'invention porte également sur un procédé d'encapsulation utilisant l'appareil selon l'invention. L'appareil et le procédé selon l'invention sont de préférence utilisés pour l'encapsulation de matériaux de déchets radioactifs, comprenant typiquement de l'uranium et/ou ses composés, et évitent la formation d'hydrure d'uranium pyrophore.
PCT/GB2011/050245 2010-02-12 2011-02-10 Appareil et procédé de mélange WO2011098817A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB1002417.2 2010-02-12
GBGB1002417.2A GB201002417D0 (en) 2010-02-12 2010-02-12 Mixing apparatus and method

Publications (1)

Publication Number Publication Date
WO2011098817A1 true WO2011098817A1 (fr) 2011-08-18

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2017064328A1 (fr) * 2015-10-15 2017-04-20 Commissariat A L'energie Atomique Et Aux Energies Alternatives Dispositif de malaxage concu notamment pour conditionner des dechets nucleaires dans du ciment, et procede

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4234447A (en) 1978-07-17 1980-11-18 The Dow Chemical Company Mixing method and container therefor
US4379081A (en) 1981-03-12 1983-04-05 Westinghouse Electric Corp. Method of encapsulating waste radioactive material
US4666676A (en) 1985-08-30 1987-05-19 The United States Of America As Represented By The United States Department Of Energy Radioactive waste processing apparatus
US20080101153A1 (en) * 2006-10-30 2008-05-01 Swisher James A Mortar mixing drum assembly
US20080119682A1 (en) * 2004-02-26 2008-05-22 Arun Wagh Aluminum Phosphate Ceramics for Waste Storage

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4234447A (en) 1978-07-17 1980-11-18 The Dow Chemical Company Mixing method and container therefor
US4379081A (en) 1981-03-12 1983-04-05 Westinghouse Electric Corp. Method of encapsulating waste radioactive material
US4666676A (en) 1985-08-30 1987-05-19 The United States Of America As Represented By The United States Department Of Energy Radioactive waste processing apparatus
US20080119682A1 (en) * 2004-02-26 2008-05-22 Arun Wagh Aluminum Phosphate Ceramics for Waste Storage
US20080101153A1 (en) * 2006-10-30 2008-05-01 Swisher James A Mortar mixing drum assembly

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
M. MCD. BAKER; L.N. LESS; S. ORMAN, URANIUM + WATER REACTION PART 1 - KINETICS, PRODUCTS AND MECHANISM TRANS. FARADAY SOC., vol. 62, 1966, pages 2513 - 2524
T.C. TOTEMEIER; R.G. PAHL: "Oxidation Kinetics of Reaction Products Formed in Uranium Metal Corrosion", September 1998, AMERICAN NUCLEAR SOCIETY

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2017064328A1 (fr) * 2015-10-15 2017-04-20 Commissariat A L'energie Atomique Et Aux Energies Alternatives Dispositif de malaxage concu notamment pour conditionner des dechets nucleaires dans du ciment, et procede
FR3042637A1 (fr) * 2015-10-15 2017-04-21 Commissariat Energie Atomique Dispositif de malaxage concu notamment pour conditionner des dechets nucleaires dans du ciment, et procede

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