WO1996041348A1 - Dispositif permettant de reduire le volume de dechets radioactifs et procede correspondant - Google Patents

Dispositif permettant de reduire le volume de dechets radioactifs et procede correspondant Download PDF

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Publication number
WO1996041348A1
WO1996041348A1 PCT/US1996/008510 US9608510W WO9641348A1 WO 1996041348 A1 WO1996041348 A1 WO 1996041348A1 US 9608510 W US9608510 W US 9608510W WO 9641348 A1 WO9641348 A1 WO 9641348A1
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WO
WIPO (PCT)
Prior art keywords
vessel
molten metal
waste
metal bath
gaseous stream
Prior art date
Application number
PCT/US1996/008510
Other languages
English (en)
Inventor
Eric P. Loewen
David D. G. Bowen
Dale S. Sleczkowski
Original Assignee
Molten Metal Technology, Inc.
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 Molten Metal Technology, Inc. filed Critical Molten Metal Technology, Inc.
Priority to AU60335/96A priority Critical patent/AU6033596A/en
Publication of WO1996041348A1 publication Critical patent/WO1996041348A1/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
    • G21F9/34—Disposal of solid waste
    • G21F9/36—Disposal of solid waste by packaging; by baling
    • 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
    • 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
    • G21F9/32—Processing by incineration

Definitions

  • Radioactive waste has many forms, such as spent fuel from nuclear reactors, and contaminated glassware and spent ion exchange resins generated by medical and chemical laboratories, and by nuclear reactors. Radioactive components are often only a small percentage, by weight, of the total weight of such wastes. The half-life of some radioactive wastes can be hundreds of thousands of years, thus requiring a permanent disposal solution.
  • radioactive waste is disposed of by burial in specially prepared landfill disposal sites, which are lined or capped, or in deep underground repositories.
  • large volumes of radioactive wastes are difficult to contain.
  • landfills can develop leaks over time, thereby allowing radioactive components to leach from the landfill site into municipal water supplies.
  • mines can become flooded and contaminate water which subsequently escapes.
  • suitable space for disposal of radioactive waste is limited.
  • the rate at which radioactive waste is generated is also much greater than the rate at which new burial sites are becoming available.
  • One attempt to treat radioactive waste includes decomposing the waste in a molten bath, such as a molten salt bath. The volume of the waste in the bath is reduced by decomposition.
  • a gaseous stream is typically discharged which includes at least one radioactive component. The gaseous stream must, therefore, be further treated before being released to the atmosphere.
  • the present invention relates to an apparatus and a method for reducing the volume of a waste which is contaminated with a radioactive component.
  • the apparatus includes a vessel having a vessel inlet for receiving the waste into the vessel and a vessel outlet for discharging a gaseous stream, the gaseous stream having been formed from the waste in the vessel.
  • a molten metal bath is within the vessel for receiving the waste from the vessel inlet and for dissolving at least a portion of the radioactive component. The molten metal bath causes a radioactive portion and a nonradioactive portion of the waste to volatilize and to migrate out of the molten metal bath, whereby the gaseous stream is formed.
  • Separating means within the vessel and between the molten metal bath and the vessel outlet separate at least a portion of the volatilized radioactive component of the gaseous stream conducted from the molten metal bath to the vessel outlet, whereby radioactive contamination of the gaseous stream is reduced and subsequent discharge of the gaseous stream from the vessel reduces the volume of the radioactivity- contaminated waste within the vessel.
  • the method includes directing the waste into a molten metal bath within a vessel, the molten metal bath dissolving at least a portion of the radioactive component and causing a nonradioactive portion of the waste to volatilize and migrate out of the molten metal bath, whereby a gaseous stream is formed. At least a portion of the volatilized radioactive component of the gaseous stream is separated from the gaseous stream, whereby radioactive contamination of the gaseous stream is reduced and subsequent discharge of the gaseous stream from the vessel reduces the volume of the radioactivity-contaminated waste within the vessel.
  • This invention has the advantage, for example, of dissolving at least a portion of a radioactive component in a bath of molten metal.
  • the composition of the bath can be adjusted to optimize the solubility of the radioactive component, and thereby minimize the amount of the radioactive component released with other gaseous components discharged from the bath. Further, volatilized radioactive components in the gaseous stream discharged from the bath are separated from nonradioactive gaseous components within the vessel containing the molten metal bath. The separated radioactive components can be in the form of particulates or condensation. The particulates, or condensation, can be returned to the molten metal bath for continued processing. Alternatively, the radioactive components can be collected separately within the vessel. In both embodiments, the radioactivity of the gaseous stream discharged from the reactor is significantly diminished, thereby substantially reducing the subsequent treatment required for the gaseous stream. Consequently, radioactive waste can be decomposed and substantially reduced in volume without generating significant volumes of other radioactive wastes by necessary treatment of streams generated during the decomposition process.
  • Figure 1 is a representation, partly in cross section and partly as a schematic, of one embodiment of the apparatus for reducing the volume of radioactive waste.
  • Figure 2 is a representation, shown in cross section, of another embodiment of the apparatus, wherein the condensing means is a packed bed elevated above the molten metal bath in the vessel.
  • Figure 3 is a cross section view of still another embodiment of the apparatus, wherein the condensing means is a packed bed of radioactive waste accumulated on a sifting screen above the molten metal bath.
  • the invention generally relates to an apparatus and a method for reducing the volume of a waste which is contaminated with a radioactive component.
  • Particularly preferred wastes for treatment by the apparatus and method of the invention are radioactive ion exchange resins.
  • a radioactive ion exchange resin can be directed into a molten bath of copper and tin.
  • the ratio of copper to tin is in a range of between about 90:10 and 40:60.
  • the system is operated at a temperature below the radionuclide boiling points of radioactive isotopes in the ion exchange resin. Radionuclides, such as cobalt, cesium, zinc and cerium will be captured in the bath because they are all soluble in the bath.
  • the bath will thermally decompose the resin, and copper oxide in the bath will provide further decomposition of the resin by the following reactions: CuO + H 2 - ⁇ Cu + H 2 0 2CuO + C ⁇ 2Cu + C0 2 CuO + CO ⁇ Cu + C0 2 xCuO + C m H n ⁇ Cu + mC0 2 + (n/2)H 2 0
  • the copper oxide is produced by injection of oxygen into a transition zone between the bath and a cold cap over the bath.
  • the cold cap removes residual volatile nuclides that are released from the bath.
  • suitable cold caps include alumina and retained resin that is suspended over the bath by a suitable support, such as a mechanical sifter.
  • Other apparatus and methods for treating wastes which include at least one radioactive component are disclosed in U.S. Patent 5,202,100.
  • vessel 10 includes lower segment 12 and upper segment 14.
  • Vessel inlet 16 is located at lower segment 14.
  • Vessel outlet 18 is located at upper segment 14.
  • Refractory crucible 20 is supported within lower segment 12 by spill container 22, which extends from below lower segment 12.
  • Crucible 20 can be removed from lower segment 12 by detaching spill container 22 from lower segment 12 and then lowering crucible 20 through vessel inlet 16 of lower segment 12.
  • Tuyere 24 at crucible 20 is suitable for directing radioactive waste into a molten metal bath within crucible 20.
  • Other devices which are suitable for directing waste into vessel 10 include a lance or baffled crucible, not shown.
  • Line 25 extends from waste source 26 to tuyere 24.
  • waste can be directed from waste source 26 through line 27 and auger 28 onto molten metal bath 30 in crucible 20.
  • An example of the suitable auger is a screw auger. Auger 28 is cooled by suitable means, not shown.
  • Lower segment 12 further includes support casing 32 and insulating liner 34.
  • Shunts 36 are located between support casing 32 and insulating liner 34 for constraining any magnetic field generated, such as that generated by an induction coil.
  • Bath coil 38 extends about insulating liner 34 and is suitable for heating or maintaining the temperature of the contents of crucible 20. Examples of suitable bath coils include electrical resistance coils, electrical, induction coils, etc.
  • Upper segment 14 of vessel 10 includes support casing 40. Annular support 42 extends from support casing 40 within upper segment 14.
  • Refractory support ring 46 is supported by annular support 42.
  • Refractory support ring 46 supports susceptor 48, which is concentric with support casing 40 of upper segment 14.
  • Refractory support ring 46 also supports susceptor liner 50, which lines an interior surface of susceptor 48.
  • Thermal insulation 52 extends about susceptor 48 and is supported by refractory support ring 46.
  • Coil 54 is wrapped around thermal insulation 52 and is suitable for heating and melting portions of waste or metal accumulated on susceptor liner 50 to thereby cause them to return to molten metal bath 30. Examples of suitable heating coils include electrical resistance coils, electrical induction coils, etc.
  • Annular spacing ring 56 extends between thermal insulation 52 and support casing 40.
  • Molten metal bath 30 is contained within crucible 20.
  • the composition of molten metal bath 30 is suitable for dissolving at least a portion of a radioactive component of a waste directed into molten metal bath 30.
  • the composition of molten metal bath 30 is also suitable for volatilizing at least a portion of a nonradioactive component of a waste directed into molten metal bath 30.
  • suitable components of molten metal bath 30 include copper, tin, iron, nickel, etc.
  • Molten metal bath 30 can include more than one metal component.
  • molten metal bath 30 can include a solution of metals, such as a solution of copper and tin.
  • the ratio of metal components of molten metal bath 30 optimizes the portion of the radioactive component of the waste which dissolves in molten metal bath 30.
  • the portion of the radioactive component dissolved in molten metal bath 30 can include a molten metal component in which the radioactive component of the waste is very soluble, but wherein the metal component has a melting point which is above the boiling point of the radioactive component under the conditions of molten metal bath 30.
  • Another molten metal component can be combined with the first molten metal component to lower the melting point of the solution of the two metals to below the boiling point of the radioactive component and thereby enable dissolution of the radioactive component in the solution.
  • a radioactive component of a waste can thereby be captured in molten metal bath 30, even though the physical properties of either metal component of the solution would not be suitable for dissolving the radioactive component.
  • radioactive components which can be dissolved in molten metal bath 30 include cobalt (Co), cesium (Cs) , zinc (Zn) , and cerium (Ce) , etc.
  • the temperature of molten metal bath 30 of molten copper is in a range of between about 500°C and 1000°C
  • molten bath 30 is formed, for example, or iron or nickel
  • the temperature of the bath is typically in a range of between about 1350 and 1650°C.
  • the temperature of the gas stream as it migrates from molten metal bath 30 to vessel outlet 18, in this embodiment typically is in a range of between about 50°C and 1200°C.
  • Separating means include cooling means at upper segment of vessel 10.
  • An example of a suitable cooling means such as is shown in Figure 1, includes cooling coil 60.
  • An example of a suitable cooling coil is a tube which conducts gas or liquid though the tube at a temperature which causes at least a portion of a volatilized radioactive portion of a waste released from molten metal bath 30 to condense.
  • gas in upper segment 14 of vessel 10 is cooled by the cooling means to a temperature in a range of between about 50°C and about 200°C.
  • Coarse filter 62 is located at vessel outlet 18.
  • An example of a suitable coarse filter is a packing material, a needle felt fabric, or a screen having a mesh size in a range of between about 400 and about 800.
  • Container 64 is suspended beneath coarse filter 62 for collecting condensate and other particulates from coarse filter 62.
  • Cooling coil 66 extends about container 64 for cooling condensate and particulates within container 64.
  • An example of a suitable cooling coil is a tube which conducts a suitable cooling gas or liquid through the tube.
  • Pulse jet 68 extends from vessel outlet 18 and is suitable for directing a gas into vessel outlet 18 to dislodge condensate and other particulates which collect on coarse filter 62.
  • HEPA filter 70 is also located at vessel outlet 18 and is suitable for collecting particulates and condensate which pass through coarse filter 62.
  • Vessel 10 and spill container 22 are within a suitable radiation shield, not shown, for shielding radiation within vessel 10. Examples of suitable radiation shields include those formed of waste, concrete, steel, etc.
  • Suitable materials of construction of support casings 32,40 for vessel 10 include, for example, stainless steel, iron, etc.
  • suitable materials of construction of thermal insulation 52 include dense alumina, carbon, etc.
  • suitable materials for construction of refractory support ring 46 include cast alumina, etc.
  • Crucible 20 can be constructed, for example, of alumina, graphite, etc.
  • the method includes directing a waste which is contaminated with a radioactive component from waste source 26 through line 27 and tuyere 24 into molten metal bath 30.
  • the waste can be directed from waste source 26 through auger 28 and into molten metal bath 30.
  • suitable wastes include ion exchange resins, carbon filters from nuclear power plants, and mixed wastes and sludges from Department of Energy facilities.
  • At least a portion of the radioactive component of the waste dissolves in molten metal bath 30. At least a portion of a non-radioactive component volatilizes within molten metal bath 30 and accumulates above molten metal bath 30 to form a gaseous stream.
  • non ⁇ radioactive components of the gaseous stream include carbon monoxide, carbon dioxide, volatilized organic compounds such as hydrogen gas, water, methane, ethane, hydrogen sulfide, sulfur dioxide, and inert gases, such as argon, used for sealing, purging equipment and aiding transport of particulate feed materials.
  • a portion of a radioactive component of the waste is included in the gaseous stream by, for example, entrainment with the non-radioactive portion or by volatilization and migration out of molten metal bath 30.
  • Cooling coil 60 causes at least a portion of the radioactive component of the gaseous stream to separate from the gaseous stream by cooling the gaseous stream to a temperature that causes the radioactive component to condense.
  • the gaseous stream is cooled to a temperature in a range of between about 20°C and 500°C.
  • the condensed radioactive component or other radioactive particulates separate from the gaseous stream by falling back into molten metal bath 30, by collecting in container 64, or by accumulating on coarse filter 62 and HEPA filter 70. Particulates can be dislodged from course filter 62 by activating pulse jet 68. Particulates dislodged from coarse filter 62 accumulate in container 64.
  • Coil 66 can be employed to further cool radioactive particulate in container 64.
  • Gas which is discharged from vessel 10 is suitably treated before discharge to the atmosphere.
  • suitable treatment of the discharged gaseous stream include scrubbing to remove components, such as sulfur dioxide, and burning to remove unwanted clean volatilized organic gases.
  • the principal components of the waste remaining within vessel 10 are radioactive components which are dissolved in molten metal bath 30.
  • Radioactive particulates in container 64 can be returned to molten metal bath 30 for further processing.
  • vessel 10 can be disassembled to remove container 64 and subsequently dispose of the radioactive contents by a suitable method.
  • molten metal bath 30 is contaminated by radioactive components which have been separated from the gas stream by the separating means and which have been returned to molten metal bath 30 as condensed particulates from the separating means.
  • Molten metal bath 30 can be disposed of by allowing the bath to cool and solidify, and thereafter removing spill container 22 from lower segment 12 and lowering crucible 20, containing the contaminated metal, out of vessel 10.
  • Crucible 20 and the contaminated metal can then be contained by conventional means, such as by storage in a suitable underground facility.
  • the separating means includes packed bed 74.
  • suitable packed beds include those formed of activated alumina, zirconium oxide, dolomite, calcium, lime, etc.
  • Packed bed 74 is spaced apart from molten metal bath 30.
  • Oxidant inlet 76 is located between molten metal bath 30 and packed bed 74.
  • Molten metal bath 30 can be formed, for example, by directing molten metal from a metal source 58 through line 59 and auger 28 into crucible 20 within lower segment 12 of vessel 10.
  • Coil 54 is employed to cool packed bed 76 to a temperature which causes at least a portion of the volatilized radioactive component in the gaseous stream discharged from molten metal bath 30 to condense and return by force of gravity to molten metal bath 30.
  • packed bed 74 is cooled to a temperature in a range of between about 20°C and about 200°C. Entrained particulates, such as radioactive particulates, from molten metal bath 30 can also be captured in packed bed 74.
  • a suitable oxidant is directed from oxidant source 78 through line 80 and oxidant inlet 76 into vessel 10.
  • the oxidant is directed into or onto molten metal bath 30 to cause reaction of the oxidant with copper in molten metal bath 30 to form copper oxide.
  • Resultant copper oxide in molten metal bath 30 reacts with waste components such as hydrogen gas, carbon, carbon monoxide and hydrocarbons to form, for example, steam and carbon dioxide gas.
  • the steam and carbon dioxide gas migrate from molten metal bath 30 to form the gaseous stream above molten metal bath 30. Copper oxide is regenerated within molten metal bath 30 by continued injection of the oxidant into molten metal bath 30.
  • the gaseous stream As the gaseous stream accumulates above molten metal bath 30, it is conducted within vessel 10 through packed bed 74 to vessel outlet 18. Radioactive components of the gaseous stream, such as volatilized radionuclides, are absorbed by packed bed 74.
  • the packing has a surface area-to-mass ratio of about 200 m 2 /gram.
  • volatilized radionuclides in the gaseous stream will be separated from the gaseous stream by redox reactions of the volatilized radionuclides with the packing. For example, alumina will react with volatilized radionuclides to separate the volatilized radionuclides from the gaseous stream.
  • the separating means includes sifting screen 86 within upper segment of vessel.
  • An oxidant is directed from oxidant source 78 through line 80 and oxidant inlet 76 into molten metal bath 30.
  • Waste is directed from waste source 26 through line 82 and waste inlet 84 into upper segment 14 of vessel 10 and onto sifting screen 86.
  • the waste accumulates on sifting screen 86 to form a packed bed 88 of waste within vessel 10.
  • the mesh size of sifting screen 86 is 60.
  • An example of a suitable material for construction of sifting screen 86 is stainless steel.
  • the waste is a resin in the form of beads that have an average diameter of about 600 microns.
  • the waste accumulates on screen 86 to form packed bed 88, a portion of the waste passes through screen 86 into molten metal bath 30 for decomposition.
  • the radioactive component of the waste dissolves in molten metal bath 30, while the organic non-radioactive component of the waste volatilizes and migrates out of molten metal bath 30 to form a gaseous stream above molten metal bath 30.
  • the gaseous stream typically will also include a volatilized radioactive component.
  • the rate of flow of waste through screen 86 from packed bed 88 to molten metal bath 30 can be adjusted by suitable means, such as a pulsing jet of gas, not shown, at screen 86.
  • Packed bed 88 is cooled by coil 54 to a temperature which causes at least a portion of radioactive components in gas discharged from molten metal bath 30 to condense and return by force of gravity from packed bed 88 to molten metal bath 30 for dissolution and continued processing.
  • packed bed 88 is cooled to a temperature in a range of between about 50°C and 200°C. Molten metal can be discharged from crucible 20 through tapping outlet 90 for suitable disposal.
  • At least a portion of radioactive components of the gaseous stream condenses within packed bed 88 and returns to molten metal bath 30 by force of gravity. As the radioactive component is removed from the gaseous stream, the remaining gas components accumulate above packed bed 88 and are conducted out of vessel 10 through HEPA filter 70 and vessel outlet 18.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Processing Of Solid Wastes (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

L'invention se rapporte à un dispositif qui permet de réduire le volume de déchets contaminés par un constituant radioactif. Le dispositif comporte un bac à bain de métal fondu dans lequel on introduit les déchets contaminés mentionnés ci-dessus. Le bain de métal fondu est approprié à la dissolution d'au moins une partie du constituant radioactif des déchets et à la mise en état volatil d'une partie non radioactive de ces déchets qui s'échappe du bain de métal fondu sous forme de flux gazeux. Un séparateur, par exemple un condenseur, est placé au-dessus du bain de métal fondu dans le bac. Ce condenseur sépare au moins une partie du constituant radioactif rendu volatil dans le flux gazeux, ce qui permet de réduire la contamination radioactive du flux en question; ensuite, l'évacuation dudit flux gazeux hors du bac réduit le volume des déchets radioactifs dans le bac.
PCT/US1996/008510 1995-06-07 1996-06-04 Dispositif permettant de reduire le volume de dechets radioactifs et procede correspondant WO1996041348A1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
AU60335/96A AU6033596A (en) 1995-06-07 1996-06-04 Apparatus and method for reducing volume of radioactive wast e

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US48637795A 1995-06-07 1995-06-07
US08/486,377 1995-06-07

Publications (1)

Publication Number Publication Date
WO1996041348A1 true WO1996041348A1 (fr) 1996-12-19

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AU (1) AU6033596A (fr)
TW (1) TW339443B (fr)
WO (1) WO1996041348A1 (fr)
ZA (1) ZA964737B (fr)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2014040140A1 (fr) * 2012-09-13 2014-03-20 Bhp Billiton Olympic Dam Corporation Pty Ltd Élimination d'impuretés radioactives contenues dans du minerai de cuivre ou du concentré de cuivre pendant ou après la fusion
WO2021175406A1 (fr) * 2020-03-02 2021-09-10 Montanuniversität Leoben Appareil et processus de traitement thermique de matière première contenant des composés du lithium et des composés du phosphore, procédé de récupération du lithium et/ou du phosphore contenus dans le matériau résiduaire de batteries au lithium-ion

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
TWI391950B (zh) * 2008-08-19 2013-04-01 Iner Aec Executive Yuan 隔離式放射性污染廢金屬熔鑄裝置
JP6721312B2 (ja) * 2015-10-16 2020-07-15 三菱重工業株式会社 放射性廃棄物の容器収容条件決定方法、放射性廃棄物収容方法および当該方法により製造される廃棄体。

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2447591A1 (fr) * 1979-01-27 1980-08-22 Daido Steel Co Ltd Procede d'entreposage de dechets radio-actifs
FR2546332A1 (fr) * 1983-05-20 1984-11-23 Wiederaufarbeitung Von Kernbre Procede de decontamination de mitraille de fer et/ou d'acier contaminee par radioactivite
US4695447A (en) * 1984-07-09 1987-09-22 Detox International Corporation Destruction of inorganic hazardous wastes
WO1993010862A1 (fr) * 1991-12-06 1993-06-10 Technological Resources Pty. Limited Traitement de dechets
EP0647598A1 (fr) * 1993-10-08 1995-04-12 Commissariat A L'energie Atomique Procédé d'incinération et de vitrification de déchets dans un creuset

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2447591A1 (fr) * 1979-01-27 1980-08-22 Daido Steel Co Ltd Procede d'entreposage de dechets radio-actifs
FR2546332A1 (fr) * 1983-05-20 1984-11-23 Wiederaufarbeitung Von Kernbre Procede de decontamination de mitraille de fer et/ou d'acier contaminee par radioactivite
US4695447A (en) * 1984-07-09 1987-09-22 Detox International Corporation Destruction of inorganic hazardous wastes
WO1993010862A1 (fr) * 1991-12-06 1993-06-10 Technological Resources Pty. Limited Traitement de dechets
EP0647598A1 (fr) * 1993-10-08 1995-04-12 Commissariat A L'energie Atomique Procédé d'incinération et de vitrification de déchets dans un creuset

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2014040140A1 (fr) * 2012-09-13 2014-03-20 Bhp Billiton Olympic Dam Corporation Pty Ltd Élimination d'impuretés radioactives contenues dans du minerai de cuivre ou du concentré de cuivre pendant ou après la fusion
WO2021175406A1 (fr) * 2020-03-02 2021-09-10 Montanuniversität Leoben Appareil et processus de traitement thermique de matière première contenant des composés du lithium et des composés du phosphore, procédé de récupération du lithium et/ou du phosphore contenus dans le matériau résiduaire de batteries au lithium-ion
WO2021175703A1 (fr) * 2020-03-02 2021-09-10 Montanuniversität Leoben Appareil et procédé de traitement thermique de matière première contenant des composés de lithium et des composés de phosphore, processus de récupération de lithium et/ou de phosphore à partir de matériau résiduel de batteries au lithium-ion

Also Published As

Publication number Publication date
AU6033596A (en) 1996-12-30
TW339443B (en) 1998-09-01
ZA964737B (en) 1997-12-08

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