EP1088314A1 - Evacuation des dechets fortement nucleaires - Google Patents
Evacuation des dechets fortement nucleairesInfo
- Publication number
- EP1088314A1 EP1088314A1 EP99921989A EP99921989A EP1088314A1 EP 1088314 A1 EP1088314 A1 EP 1088314A1 EP 99921989 A EP99921989 A EP 99921989A EP 99921989 A EP99921989 A EP 99921989A EP 1088314 A1 EP1088314 A1 EP 1088314A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- mineral
- assemblage
- crystals
- mineral assemblage
- closely related
- 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- Withdrawn
Links
- 239000002699 waste material Substances 0.000 title description 6
- 229910052500 inorganic mineral Inorganic materials 0.000 claims abstract description 86
- 239000011707 mineral Substances 0.000 claims abstract description 86
- 239000013078 crystal Substances 0.000 claims abstract description 50
- 239000002927 high level radioactive waste Substances 0.000 claims abstract description 48
- GWEVSGVZZGPLCZ-UHFFFAOYSA-N titanium dioxide Inorganic materials O=[Ti]=O GWEVSGVZZGPLCZ-UHFFFAOYSA-N 0.000 claims abstract description 28
- 239000010936 titanium Substances 0.000 claims description 26
- 239000000203 mixture Substances 0.000 claims description 24
- 238000000034 method Methods 0.000 claims description 15
- MCMNRKCIXSYSNV-UHFFFAOYSA-N Zirconium dioxide Chemical compound O=[Zr]=O MCMNRKCIXSYSNV-UHFFFAOYSA-N 0.000 claims description 11
- 230000008569 process Effects 0.000 claims description 11
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 claims description 9
- 238000010438 heat treatment Methods 0.000 claims description 9
- 239000000243 solution Substances 0.000 claims description 8
- 229910052719 titanium Inorganic materials 0.000 claims description 8
- 239000006104 solid solution Substances 0.000 claims description 6
- 229910009973 Ti2O3 Inorganic materials 0.000 claims description 5
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 claims description 5
- 229910052593 corundum Inorganic materials 0.000 claims description 5
- 239000011521 glass Substances 0.000 claims description 5
- 238000010348 incorporation Methods 0.000 claims description 5
- 229910001845 yogo sapphire Inorganic materials 0.000 claims description 5
- ODINCKMPIJJUCX-UHFFFAOYSA-N Calcium oxide Chemical compound [Ca]=O ODINCKMPIJJUCX-UHFFFAOYSA-N 0.000 claims description 4
- 229910052782 aluminium Inorganic materials 0.000 claims description 3
- 229910052788 barium Inorganic materials 0.000 claims description 3
- 238000001816 cooling Methods 0.000 claims description 3
- 230000003100 immobilizing effect Effects 0.000 claims description 3
- 239000002245 particle Substances 0.000 claims description 3
- GQUJEMVIKWQAEH-UHFFFAOYSA-N titanium(III) oxide Chemical compound O=[Ti]O[Ti]=O GQUJEMVIKWQAEH-UHFFFAOYSA-N 0.000 claims description 3
- 239000004411 aluminium Substances 0.000 claims description 2
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 2
- DSAJWYNOEDNPEQ-UHFFFAOYSA-N barium atom Chemical compound [Ba] DSAJWYNOEDNPEQ-UHFFFAOYSA-N 0.000 claims description 2
- 150000004649 carbonic acid derivatives Chemical class 0.000 claims description 2
- 239000000499 gel Substances 0.000 claims description 2
- 238000002156 mixing Methods 0.000 claims description 2
- 239000011575 calcium Substances 0.000 description 10
- 230000002285 radioactive effect Effects 0.000 description 10
- 239000000463 material Substances 0.000 description 7
- 229910052770 Uranium Inorganic materials 0.000 description 6
- 238000013459 approach Methods 0.000 description 6
- 229910052791 calcium Inorganic materials 0.000 description 6
- 238000006467 substitution reaction Methods 0.000 description 6
- 229910052778 Plutonium Inorganic materials 0.000 description 5
- 230000004992 fission Effects 0.000 description 5
- 229910052751 metal Inorganic materials 0.000 description 5
- 239000002184 metal Substances 0.000 description 5
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 5
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 4
- OYPRJOBELJOOCE-UHFFFAOYSA-N Calcium Chemical compound [Ca] OYPRJOBELJOOCE-UHFFFAOYSA-N 0.000 description 3
- 229910052768 actinide Inorganic materials 0.000 description 3
- 150000001255 actinides Chemical class 0.000 description 3
- 230000015572 biosynthetic process Effects 0.000 description 3
- 238000009472 formulation Methods 0.000 description 3
- 238000000227 grinding Methods 0.000 description 3
- 239000008240 homogeneous mixture Substances 0.000 description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 description 3
- 238000003756 stirring Methods 0.000 description 3
- OGIDPMRJRNCKJF-UHFFFAOYSA-N titanium oxide Inorganic materials [Ti]=O OGIDPMRJRNCKJF-UHFFFAOYSA-N 0.000 description 3
- 229910016010 BaAl2 Inorganic materials 0.000 description 2
- 238000001354 calcination Methods 0.000 description 2
- 229910010293 ceramic material Inorganic materials 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 238000005304 joining Methods 0.000 description 2
- RVTZCBVAJQQJTK-UHFFFAOYSA-N oxygen(2-);zirconium(4+) Chemical class [O-2].[O-2].[Zr+4] RVTZCBVAJQQJTK-UHFFFAOYSA-N 0.000 description 2
- 238000005192 partition Methods 0.000 description 2
- 238000010587 phase diagram Methods 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 229910052761 rare earth metal Inorganic materials 0.000 description 2
- 239000011435 rock Substances 0.000 description 2
- 238000003786 synthesis reaction Methods 0.000 description 2
- 229910052726 zirconium Inorganic materials 0.000 description 2
- 229910001928 zirconium oxide Inorganic materials 0.000 description 2
- 229910052695 Americium Inorganic materials 0.000 description 1
- 229910052685 Curium Inorganic materials 0.000 description 1
- 229910052781 Neptunium Inorganic materials 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- 239000000654 additive Substances 0.000 description 1
- 230000000996 additive effect Effects 0.000 description 1
- 150000001450 anions Chemical class 0.000 description 1
- 239000005388 borosilicate glass Substances 0.000 description 1
- 238000009933 burial Methods 0.000 description 1
- WUKWITHWXAAZEY-UHFFFAOYSA-L calcium difluoride Chemical compound [F-].[F-].[Ca+2] WUKWITHWXAAZEY-UHFFFAOYSA-L 0.000 description 1
- 150000001768 cations Chemical class 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000010436 fluorite Substances 0.000 description 1
- 238000001513 hot isostatic pressing Methods 0.000 description 1
- 238000011835 investigation Methods 0.000 description 1
- 238000002386 leaching Methods 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- SOQBVABWOPYFQZ-UHFFFAOYSA-N oxygen(2-);titanium(4+) Chemical class [O-2].[O-2].[Ti+4] SOQBVABWOPYFQZ-UHFFFAOYSA-N 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 150000002910 rare earth metals Chemical class 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
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
Definitions
- This invention relates to the treatment and disposal of high level radioactive wastes (HLW) from nuclear reactors, and in particular relates to a mineral assemblage incorporating HLW, to a process for producing such a mineral assemblage and to a process for immobilisation of HLW in a mineral assemblage which will retain dangerously radioactive isotopes in the waste for periods sufficient to ensure that they do not re-enter the biosphere prior to their effective decay.
- HLW high level radioactive wastes
- HLW such as spent fuel from nuclear reactors, as are used in commercial power plants, contains a wide range of highly radioactive isotopes. These radioactive isotopes emit radiation which is dangerous to living organisms and must be disposed of in such a manner that they do not re-enter the biosphere during their effective decay periods.
- One group of these isotopes is formed by the fission of uranium (and plutonium). From the disposal point of view the most important components formed by such fission are 137Cs, 90Sr and the radio-active isotopes of the actinide elements.
- the fission products 137Cs and 90Sr have half lives of about 30 years and must be contained for a period of about 600 years before they decay to safe levels.
- the dominant radioactive species in the waste are the actinide elements, principally isotopes of Pu, Am, Cm and Np which decay by the emission of alpha particles.
- the activity of the waste becomes comparable to that of the original uranium which was mined to produce the nuclear fuel. This is usually taken to be a suitable time for containment.
- Spent fuel rods are generally reprocessed to recover plutonium and unused uranium. During this reprocessing the spent fuel rods are placed in cooling ponds for several years to permit the decay of several highly radioactive, short-lived fission products. Subsequently, the rods are chopped into sections and dissolved in nitric acid. Plutonium and uranium are recovered from the solution, the remainder of which is a HLW solution. In most cases these HLW solutions are transformed initially into a solid, insoluble form. This is accomplished in the first instance by evaporating the HLW solution to dryness and calcining the material to produce a fine-grained mixture of radioactive oxides-called "calcine" . Calcine is an unsatisfactory form for disposal because of its low density, low thermal conductivity and high solubility. Thus, further processing of this material is necessary for its safe disposal.
- a synthetic rock known as SYNROC is described for example in United States Patent No. 4,274,976.
- the SYNROC materials are a mineral assemblage containing well formed crystals capable of providing lattice sites in which the elements of the HLW are securely bound.
- the crystals belong to or possess crystal structures closely related to at least two of the titanate mineral classes selected from the group consisting of perovskite (CaTiO 3 ), zirconolite (CaZrTi 2 O 7 ) and hollandite-type (BaAl 2 Ti 6 O 16 ) mineral classes.
- SYNROC materials have been extensively investigated and are predicted to provide stable immobilisation of HLW elements, allowing the assemblage to be safely buried in an appropriate geological environment. Consequently, SYNROC materials are in the process of commercial development for the storage of HLW wastes.
- the extensive investigations into the SYNROC materials has led to the incorporation of rutile, and often with a small percentage of titanium metal. It has been reported that the preferred formulations of SYNROC have been designed to avoid destabilisation and incorporate an excess of rutile TiO 2 such that rutile is the major phase of the SYNROC assemblage.
- SYNROC assemblages are preferably formulated with substantial amounts of rutile in order to improve stability, rutile plays little or no part in taking up the HLW.
- the present invention is directed to an alternate assemblage which does not contain significant quantities of rutile.
- mineral assemblages which include calzirtite provide at least a useful alternative to the previously disclosed SYNROC compositions.
- this invention provides a mineral assemblage comprising crystals belonging to or possessing crystal structures closely related to both the perovskite and zirconoUte mineral classes and further comprising crystals belonging to or possessing crystal structures closely related to the calzirtite mineral class wherein the mineral assemblage incorporates high-level radioactive wastes immobilized therein.
- a mineral complex which forms part of a mineral assemblage is generally qualified by the term "crystals belonging to or possessing crystal structures closely related to " .
- This term will be understood by those skilled in the art to refer not only to the mineral complex having an ideal crystal structure but also to mineral complexes incorporating additional elements therein, such as elements replacing one or more of the elements of the ideal crystal structure or additional elements retained interstitially within the ideal crystal structure.
- the additional elements may give rise to a departure of the crystal structure from the ideal.
- Perovskite is a complex of calcium and titanium oxides having an ideal formulation CaTiO 3 .
- Perovskite-type structures are adopted by ABO 3 compounds such as CaTiO 3 perovskite.
- the ideal CaTiO 3 component is of orthorhombic symmetry.
- Zirconolite is a complex of calcium, titanium and zirconium oxides having an ideal formula CaZrTi 2 O 7 .
- Zirconolite may be more generally described as CaZr x Ti 2 . x O 7 and is a generic term to encompass a group of closely related structural polytypes which occur in monoclinic, trigonal and orthorhombic polytypes.
- Calzirtite is a complex of calcium, titanium and zirconium oxides having an ideal formula Ca 2 Zr 5 Ti 2 O 16 .
- Calzirtite may be more generally described as Ca 2 Zr 5 .
- x Ti x O 16 is a generic term to encompass a group of closely related structural polytypes. Both calzirtite and zirconolite are anion deficient fluorite-related superstructure phases.
- the cations occupy fluorite-type positions in the tetragonal cell.
- the mineral assemblages of the present invention preferably comprise crystals of mineral complexes which are relatively small in size, in order to maximise diffusion controlled uniformity of HLW incorporation into desired crystalline structures.
- the crystals of the mineral assemblages are generally of up to two hundred microns in size.
- titanium in the crystal structures of the crystals of the mineral assemblages of the present invention where the titanium is of at least two different co-existing valency states permits a more stable immobilization of the radioactive isotopes of the HLW within the mineral assemblage.
- Ti 3+ and Ti 4+ is particularly preferred.
- Ti 2 O 3 may be present in solid solution in the crystals of the mineral assemblage.
- Mineral complexes incorporating other elements may advantageously be incorporated into the mineral assemblages of the present invention. It is preferred that mineral complexes which incorporate barium and/or aluminium be incorporated into the mineral assemblages. Hollandite of general composition AJB y Cg. y O,,;, ideal end member (BaAl 2 Ti 6 O 16 ) is particularly preferred as a host phase for HLW elements together with perovskite, zirconolite and calzirtite. Under certain conditions of production, other Ba, Al phases may also occur. The presence of these elements and crystal structures is particularly preferred for hosting certain HLW elements, which otherwise do not readily partition into the other phases. Other hollandite-type mineral complexes which may be included within the mineral assemblages include K and Sr replacing Ba.
- the assemblage includes at least some of each of the calzirtite, zirconolite, perovskite and hollandite. More preferably, the assemblage includes at least 10 weight percent of each of calzirtite, zirconolite, perovskite and hollandite.
- the mineral assemblages may include at least 20 weight percent HLW.
- the present invention also provides a process for immobilizing high level radio-active waste comprising the steps of:
- the high level radio-active waster calcine is generally formed from a solution of HLW such as may be produced from commercial nuclear power plants.
- the calcine may typically be formed by evaporating the solution of HLW to dryness and calcining the material to form a fine-grained mixture of radio-active oxides.
- the composition of a typical HLW calcine resulting from the fission of uranium (and plutonium) is set our in table 1 below: TABLE 1
- HLW elements may be incorporated into this mineral assembly by adding an HLW calcine mixture prior to heating.
- the HLW calcine may make up, up to about 20% by weight of the mixture of oxides.
- the oxides may be mixed by any convenient means and heated by processes as are known to those skilled in the art.
- the oxides are selected, having regard to their composition and their relative proportions so as to form the desired mineral assemblage.
- the oxides and amounts will be in part dependent upon the processing conditions and it will be apparent to those skilled in the art how to make such selections in order to obtain the mineral assemblages hereinabove described.
- Oxides which may be used in the process of the present invention include CaO, ZrO 2 , TiO 2 , TiO 2 - Ti 2 O 3 solution, Al 2 O 3 and BaO, oxides, carbonates, gels or glasses.
- the heating can be to either subsolidus or above solidus conditions. Heating to above solidus conditions may allow the mineral assemblage to be produced in less time.
- a mineral assemblage is preferably formed by heating the mixture of oxides to subsolidus conditions.
- the formation of the mineral assemblage under subsolidus conditions requires the mixture be maintained at an elevated temperature, say 1000 to 1600°C for a period sufficient for the mineral assemblage to achieve phase equilibrium and have the crystals of the desired particle size.
- the preferred time of heating varies with temperature. It can be at a temperature of 1000°C for 36 hours or up to a temperature of 1600°C for one four as well as intermediate temperatures and heating times to produce desirable results. It is then allowed to cool to ambient temperature.
- the assemblage of this invention can be formed under pressure of one atmosphere or by using hot isostatic pressing techniques.
- a reducing environment is preferably used for the incorporation Ti in a number of different valency states. This can be achieved by several methods under appropriate reducing atmospheric conditions. One approach is to take TiO 2 and under appropriate atmosphere convert it into a Magnelli phase with the desired Ti 4+ -Ti 3+ solid solution. This is then added to the other oxides prior to synthesis. Another approach is to add Ti 4+ directly to the other oxides and convert some of it into Ti 3+ prior to heating (with or without Ti metal).
- Figure 1 shows a molecular proportion phase diagram which illustrates the mineral assemblages of the present invention. Mineral assemblages according to this invention are within the area bordered by the lines respectively joining points marked as calzirtite, zirconolite and perovskite. The assemblages may also include hollandite (Ba Al 2 Ti 6 O 16 ). Previous SYNROC compositions have fallen into the area bounded by the lines connecting zirconolite, rutile and perovskite.
- Figure 2 shows a molecular proportion phase diagram which incorporates Ti.
- the mineral assemblages which include perovskite, zirconolite and calzirtite may also include Ti 2 O 3 in solid solution, in the absence of rutile.
- the mineral assemblages according to the present invention contain a number of coexisting titanate and hollandite-type phases, in which calzirtite, zirconolite, perovskite and preferably a Ba-phase such as hollandite are prevalent. Other Ba-phases as well as baddeleyite, srilankite may occur under certain conditions. These phases, when synthesised under appropriate conditions, substitute HLW elements into their crystalline structures by a variety of substitution mechanisms. This results in significant departure from ideal end member compositions. Without wishing to be bound by theory, it is believed that the HLW elements are immobilized in a number of coexisting minerals which depart from ideal compositions due to their abilities to accommodate HLW elements into their crystalline structures.
- the mineral assemblages of the present invention is believed to incorporate significant HLW components through a variety of substitutions for Ca, Zr, Ti, Ba, Al in the various crystal structure sites.
- Certain HLW elements partition differently into the different phases, based on crystal chemical principles. These substitutions range from simple replacements (one element for another) through to coupled substitutions such that several HLW elements replace several element on different crystallographic sites in the ideal crystal structures.
- both Ca and Ti may be substituted to varying amounts by certain HLW additive elements. This may be by either element-element replacements (for example Ca replaced by Sr) or else more coupled substitutions involving rare earth elements, U, Na) as well as Ti 3+ . These substitutions can result in symmetries other than orthorhombic (such as cubic, rhombohedral).
- HLW elements such as rare earth and actinide elements may be accommodated within the structure.
- the mixture was heated in a metal vessel at a temperature of 1300°C for 6 hours and allowed to cool to ambient temperature.
- the resultant mineral assemblage had the following crystals present in the proportions listed below:
- the mixture was heated in a metal vessel at a temperature of 1300°C for 6 hours and allowed to cool to ambient temperature.
- the resultant mineral assemblage had the following crystals present in the proportions listed below:
Landscapes
- Chemical & Material Sciences (AREA)
- Inorganic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
L'invention concerne des déchets fortement radioactifs pouvant être immobilisés dans des assemblages de minéraux contenant peu ou pas de rutile. L'assemblage minéral comprend des cristaux appartenant à ou possédant des structures cristallines très proches des minéraux de la classe de la pérovskite et zirconolite et comprenant aussi des cristaux présentant des structures cristallines très proches de des minéraux de type calzirtite. Cet assemblage renferme des déchets fortement radioactifs.
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| AUPP355598 | 1998-05-18 | ||
| AUPP3555A AUPP355598A0 (en) | 1998-05-18 | 1998-05-18 | High level nuclear waste disposal |
| PCT/AU1999/000376 WO1999060577A1 (fr) | 1998-05-18 | 1999-05-18 | Evacuation des dechets fortement nucleaires |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| EP1088314A1 true EP1088314A1 (fr) | 2001-04-04 |
Family
ID=3807808
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP99921989A Withdrawn EP1088314A1 (fr) | 1998-05-18 | 1999-05-18 | Evacuation des dechets fortement nucleaires |
Country Status (5)
| Country | Link |
|---|---|
| EP (1) | EP1088314A1 (fr) |
| JP (1) | JP2002516397A (fr) |
| AU (1) | AUPP355598A0 (fr) |
| CA (1) | CA2332842A1 (fr) |
| WO (1) | WO1999060577A1 (fr) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB9926674D0 (en) * | 1999-11-12 | 2000-01-12 | British Nuclear Fuels Plc | Encapsulation of waste |
| GB2367418A (en) * | 2000-08-19 | 2002-04-03 | British Nuclear Fuels Plc | Encapsulation of waste |
| US8754282B2 (en) * | 2011-06-02 | 2014-06-17 | American Isostatic Presses, Inc. | Methods of consolidating radioactive containing materials by hot isostatic pressing |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4274976A (en) * | 1978-07-14 | 1981-06-23 | The Australian National University | Treatment of high level nuclear reactor wastes |
| US4329248A (en) * | 1979-03-01 | 1982-05-11 | The Australian National University | Process for the treatment of high level nuclear wastes |
| US5656009A (en) * | 1995-08-11 | 1997-08-12 | Battelle Memorial Institute | Process for immobilizing plutonium into vitreous ceramic waste forms |
| US5597516A (en) * | 1995-08-11 | 1997-01-28 | Battelle Memorial Institute | Process for immobilizing plutonium into vitreous ceramic waste forms |
-
1998
- 1998-05-18 AU AUPP3555A patent/AUPP355598A0/en not_active Abandoned
-
1999
- 1999-05-18 JP JP2000550110A patent/JP2002516397A/ja not_active Withdrawn
- 1999-05-18 CA CA002332842A patent/CA2332842A1/fr not_active Abandoned
- 1999-05-18 WO PCT/AU1999/000376 patent/WO1999060577A1/fr not_active Ceased
- 1999-05-18 EP EP99921989A patent/EP1088314A1/fr not_active Withdrawn
Non-Patent Citations (1)
| Title |
|---|
| See references of WO9960577A1 * |
Also Published As
| Publication number | Publication date |
|---|---|
| WO1999060577A1 (fr) | 1999-11-25 |
| JP2002516397A (ja) | 2002-06-04 |
| AUPP355598A0 (en) | 1998-06-11 |
| CA2332842A1 (fr) | 1999-11-25 |
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