WO1996032729A1 - Procede de traitement de combustible oxyde nucleaire - Google Patents
Procede de traitement de combustible oxyde nucleaire Download PDFInfo
- Publication number
- WO1996032729A1 WO1996032729A1 PCT/GB1996/000872 GB9600872W WO9632729A1 WO 1996032729 A1 WO1996032729 A1 WO 1996032729A1 GB 9600872 W GB9600872 W GB 9600872W WO 9632729 A1 WO9632729 A1 WO 9632729A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- carbonate
- oxide
- uranium
- fuel
- salt
- Prior art date
Links
- 238000000034 method Methods 0.000 title claims abstract description 42
- 238000012545 processing Methods 0.000 title claims abstract description 14
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 8
- 229910052770 Uranium Inorganic materials 0.000 claims abstract description 31
- 150000001875 compounds Chemical class 0.000 claims abstract description 4
- 229910000288 alkali metal carbonate Inorganic materials 0.000 claims abstract description 3
- 150000008041 alkali metal carbonates Chemical class 0.000 claims abstract description 3
- 239000000446 fuel Substances 0.000 claims description 38
- 238000005868 electrolysis reaction Methods 0.000 claims description 34
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 28
- 150000003839 salts Chemical class 0.000 claims description 19
- 229910052778 Plutonium Inorganic materials 0.000 claims description 18
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 17
- BVKZGUZCCUSVTD-UHFFFAOYSA-L Carbonate Chemical compound [O-]C([O-])=O BVKZGUZCCUSVTD-UHFFFAOYSA-L 0.000 claims description 16
- 239000000203 mixture Substances 0.000 claims description 15
- 150000005323 carbonate salts Chemical class 0.000 claims description 10
- 239000011833 salt mixture Substances 0.000 claims description 10
- 238000006243 chemical reaction Methods 0.000 claims description 7
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 claims description 6
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 claims description 6
- BWHMMNNQKKPAPP-UHFFFAOYSA-L potassium carbonate Chemical compound [K+].[K+].[O-]C([O-])=O BWHMMNNQKKPAPP-UHFFFAOYSA-L 0.000 claims description 6
- 229910000439 uranium oxide Inorganic materials 0.000 claims description 6
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 claims description 5
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical group O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims description 4
- 229910001508 alkali metal halide Inorganic materials 0.000 claims description 4
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 4
- 229910052760 oxygen Inorganic materials 0.000 claims description 4
- 239000001301 oxygen Substances 0.000 claims description 4
- FGIUAXJPYTZDNR-UHFFFAOYSA-N potassium nitrate Chemical compound [K+].[O-][N+]([O-])=O FGIUAXJPYTZDNR-UHFFFAOYSA-N 0.000 claims description 4
- 239000000843 powder Substances 0.000 claims description 4
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims description 3
- 230000002378 acidificating effect Effects 0.000 claims description 3
- 150000008045 alkali metal halides Chemical class 0.000 claims description 3
- 229910052808 lithium carbonate Inorganic materials 0.000 claims description 3
- 239000007800 oxidant agent Substances 0.000 claims description 3
- 229910000027 potassium carbonate Inorganic materials 0.000 claims description 3
- 229910052708 sodium Inorganic materials 0.000 claims description 3
- 229910000029 sodium carbonate Inorganic materials 0.000 claims description 3
- 239000003513 alkali Substances 0.000 claims description 2
- 239000000374 eutectic mixture Substances 0.000 claims description 2
- 235000010333 potassium nitrate Nutrition 0.000 claims description 2
- 239000004323 potassium nitrate Substances 0.000 claims description 2
- CHWRSCGUEQEHOH-UHFFFAOYSA-N potassium oxide Chemical compound [O-2].[K+].[K+] CHWRSCGUEQEHOH-UHFFFAOYSA-N 0.000 claims description 2
- 229910001950 potassium oxide Inorganic materials 0.000 claims description 2
- 239000000377 silicon dioxide Substances 0.000 claims description 2
- PFUVRDFDKPNGAV-UHFFFAOYSA-N sodium peroxide Chemical compound [Na+].[Na+].[O-][O-] PFUVRDFDKPNGAV-UHFFFAOYSA-N 0.000 claims description 2
- 235000011181 potassium carbonates Nutrition 0.000 claims 2
- YWEUIGNSBFLMFL-UHFFFAOYSA-N diphosphonate Chemical compound O=P(=O)OP(=O)=O YWEUIGNSBFLMFL-UHFFFAOYSA-N 0.000 claims 1
- DLYUQMMRRRQYAE-UHFFFAOYSA-N phosphorus pentoxide Inorganic materials O1P(O2)(=O)OP3(=O)OP1(=O)OP2(=O)O3 DLYUQMMRRRQYAE-UHFFFAOYSA-N 0.000 claims 1
- 235000011182 sodium carbonates Nutrition 0.000 claims 1
- DNYWZCXLKNTFFI-UHFFFAOYSA-N uranium Chemical compound [U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U] DNYWZCXLKNTFFI-UHFFFAOYSA-N 0.000 abstract 2
- 238000004090 dissolution Methods 0.000 description 12
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 description 11
- 229910052793 cadmium Inorganic materials 0.000 description 9
- 239000000463 material Substances 0.000 description 9
- 239000000047 product Substances 0.000 description 7
- 239000011734 sodium Substances 0.000 description 7
- -1 alkali metal halide salts Chemical class 0.000 description 6
- 229910052751 metal Inorganic materials 0.000 description 6
- 239000002184 metal Substances 0.000 description 6
- 239000002699 waste material Substances 0.000 description 6
- 239000000126 substance Substances 0.000 description 5
- 229910052781 Neptunium Inorganic materials 0.000 description 4
- 230000004992 fission Effects 0.000 description 4
- 238000010438 heat treatment Methods 0.000 description 4
- LFNLGNPSGWYGGD-UHFFFAOYSA-N neptunium atom Chemical compound [Np] LFNLGNPSGWYGGD-UHFFFAOYSA-N 0.000 description 4
- 238000012958 reprocessing Methods 0.000 description 4
- ZLMJMSJWJFRBEC-UHFFFAOYSA-N Potassium Chemical compound [K] ZLMJMSJWJFRBEC-UHFFFAOYSA-N 0.000 description 3
- 229910052700 potassium Inorganic materials 0.000 description 3
- 239000011591 potassium Substances 0.000 description 3
- 230000002285 radioactive effect Effects 0.000 description 3
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 2
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 2
- 238000007792 addition Methods 0.000 description 2
- 238000005275 alloying Methods 0.000 description 2
- 150000004649 carbonic acid derivatives Chemical class 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000000605 extraction Methods 0.000 description 2
- 150000004673 fluoride salts Chemical class 0.000 description 2
- 230000008018 melting Effects 0.000 description 2
- 238000002844 melting Methods 0.000 description 2
- 229910017604 nitric acid Inorganic materials 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 229910000925 Cd alloy Inorganic materials 0.000 description 1
- KRHYYFGTRYWZRS-UHFFFAOYSA-M Fluoride anion Chemical compound [F-] KRHYYFGTRYWZRS-UHFFFAOYSA-M 0.000 description 1
- 229910001184 Np alloy Inorganic materials 0.000 description 1
- OAICVXFJPJFONN-UHFFFAOYSA-N Phosphorus Chemical compound [P] OAICVXFJPJFONN-UHFFFAOYSA-N 0.000 description 1
- 229910052768 actinide Inorganic materials 0.000 description 1
- 150000001255 actinides Chemical class 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 238000010923 batch production Methods 0.000 description 1
- SHZGCJCMOBCMKK-KGJVWPDLSA-N beta-L-fucose Chemical class C[C@@H]1O[C@H](O)[C@@H](O)[C@H](O)[C@@H]1O SHZGCJCMOBCMKK-KGJVWPDLSA-N 0.000 description 1
- 238000009933 burial Methods 0.000 description 1
- 239000006227 byproduct Substances 0.000 description 1
- 239000007795 chemical reaction product Substances 0.000 description 1
- 150000003841 chloride salts Chemical class 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000008021 deposition Effects 0.000 description 1
- 230000001627 detrimental effect Effects 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005496 eutectics Effects 0.000 description 1
- 239000012467 final product Substances 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000002386 leaching Methods 0.000 description 1
- XGZVUEUWXADBQD-UHFFFAOYSA-L lithium carbonate Chemical compound [Li+].[Li+].[O-]C([O-])=O XGZVUEUWXADBQD-UHFFFAOYSA-L 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 229910021645 metal ion Inorganic materials 0.000 description 1
- 229910044991 metal oxide Inorganic materials 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- ZQPKENGPMDNVKK-UHFFFAOYSA-N nitric acid;plutonium Chemical compound [Pu].O[N+]([O-])=O ZQPKENGPMDNVKK-UHFFFAOYSA-N 0.000 description 1
- 239000011574 phosphorus Substances 0.000 description 1
- 229910052698 phosphorus Inorganic materials 0.000 description 1
- 230000035755 proliferation Effects 0.000 description 1
- 238000000746 purification Methods 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 238000004064 recycling Methods 0.000 description 1
- 239000011780 sodium chloride Substances 0.000 description 1
- 238000000638 solvent extraction Methods 0.000 description 1
- 231100000331 toxic Toxicity 0.000 description 1
- 230000002588 toxic effect Effects 0.000 description 1
- 231100000419 toxicity Toxicity 0.000 description 1
- 230000001988 toxicity Effects 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/01—Oxides; Hydroxides
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0213—Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/04—Obtaining plutonium
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/48—Non-aqueous processes
-
- 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
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- 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
Definitions
- the present invention relates to the processing of irradiated oxide nuclear fuel material.
- Nuclear fuels discharged after irradiation in a nuclear
- salt processing techniques is that the molten salt materials are highly corrosive to plant and waste containers and are also, in the case of fluorides, highly
- a method for the processing of oxide nuclear fuel containing uranium including the step of reacting the oxide with a fused alkali metal carbonate to produce a compound which may be further processed so as to extract at
- the carbonate may comprise sodium carbonate, Na,C0 3 ;
- Mixtures may be chosen on the basis of their
- Such chemicals may include an oxidising agent such as
- air or oxygen may be passed
- the molten carbonate salt may also contain sodium hydroxide or other alkali compound as appropriate in order to assist
- the molten carbonate salt may also include a proportion of alkali metal halide such as sodium chloride or potassium
- fluoride for example, in order to assist dissolution of the oxide fuel into the carbonate.
- Dissolution of the irradiated fuel material may be enhanced by a further processing step of initially oxidising the fuel oxide to convert it into uranium oxide powder of composition U 3 0 3 or U0 3 by known techniques.
- the mixture may be further processed so as to remove the uranium, plutonium and neptunium, if present, from the mixture. Such further processing may normally
- a first electrolysis stage may be to remove at least a
- Irradiated thermal reactor fuel normally has in the region of 1% plutonium therein whereas new fuel may have about 6% plutonium or more therein. Therefore, electrolysis may preferably be continued so as to increase the relative proportion of plutonium to uranium to substantially above 6%.
- a second electrolysis stage may employ a different cathode so as to allow the extraction of at least the plutonium, the plutonium and most of the remaining uranium migrating thereto and alloying therewith.
- a cathode may comprise, for example, molten cadmium metal.
- the resulting cadmium/ plutonium/ uranium (/neptunium) cathode is removed and the unwanted cadmium removed, for example, by distilling the cadmium off.
- the remaining fuel metal elements being further processed into the desired final fuel oxide
- the wastes produced are less mobile in a disposal environment than the alkali metal halides of the prior art and are thus easier to dispose of.
- the method of the present invention may be operated as a batch process, the process employing a first step of making a required fused carbonate salt mixture and adding the irradiated fuel thereto in the required proportion to achieve at least partial dissolution of the fuel oxide therein; a second step may be the first electrolysis stage
- a third step may be the second electrolysis stage as described above,- and, a fourth step may include the further processing of the resulting uranium and/or plutonium and any other metal by-products into the final desired products such as U0 2 powder or PuO, powder for the manufacture of new fuel rods for example.
- the first and second electrolysis stages may be carried out
- each stage, or separate electrolysis cells may be employed
- the carbonate salt may be melted and maintained molten by
- the molten cadmium cathode may be maintained molten by the
- Such oxides may include silica and phosphorus
- Figure 1 shows a flow diagram of an embodiment of a
- Figure 2 shows a schematic cross section of an electrolysis cell for carrying out a first electrolysis stage,- and
- Figure 3 which shows a schematic cross section of an electrolysis cell for carrying out a second electrolysis stage.
- Irradiated fuel rods are first chopped into
- breached fuel rods are added to the fused carbonate mixture
- molten metal cathode such as cadmium
- the extracted plutonium/ uranium/ neptunium/ cadmium alloy from 22 is then processed by heating and distilling off the cadmium (24) to leave the required product (26) .
- Figure 2 shows a schematic cross section through an
- the cell for carrying out a first electrolysis stage.
- the cell comprises a vessel 40 having therein a
- fused carbonate salt mixture 42 in which an irradiated oxide fuel has been reacted so as to achieve at least partial dissolution.
- An anode 44 and cathode 46 are provided together with a power supply and control apparatus 48.
- Heaters 50 are provided to melt and maintain molten the salt/oxide fuel mixture 42. Electrolysis of the mixture 42 results in uranium or uranium oxide 52 being deposited on
- the cathode 46 so as to deplete the uranium content in the mixture 42. If all of the oxide fuel was not initially reacted or dissolved in the fused carbonate salt, as the uranium content drops during electrolysis, more of the oxide fuel will react with the salt mixture or reacted but
- the initial reaction of the oxide fuel with the carbonate and oxygen, either from an oxide in the fused salt mixture or from air or oxygen passed through the molten salt may be typically described by the reaction:
- reaction In the first electrolysis stage to extract uranium, the reaction may be described by:
- Figure 3 shows a schematic cross section through an electrolysis cell for carrying out a second electrolysis stage of the method according to the present invention.
- a cell comprises a vessel 70 having heaters 72 to maintain molten a salt mixture 74 resulting from the first electrolysis stage as described above with reference to
- An anode 78 and power supply and control apparatus 80 are provided.
- plutonium ions and uranium ions (and neptunium ions if present) migrate to the molten cadmium cathode and alloy therewith.
- the cadmium cathode is removed and the cadmium metal removed by distilling off at high temperature to leave behind the required metals which may be further processed according to known techniques to produce new fuel rods.
- the reaction to extract plutonium from the fused salt during the second electrolysis stage may be of the form:
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Organic Chemistry (AREA)
- Geology (AREA)
- Physics & Mathematics (AREA)
- Environmental & Geological Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Inorganic Chemistry (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Electrolytic Production Of Metals (AREA)
Abstract
Cette invention concerne un procédé destiné au traitement de combustible oxyde nucléaire contenant de l'uranium, ce procédé consistant à faire réagir l'oxyde avec un carbonate fondu de métal alcalin pour obtenir un composé qui peut subir un traitement ultérieur en vue de l'extraction d'au moins une partie de l'uranium et d'autres produits dérivés.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB9507644.4 | 1995-04-12 | ||
| GB9507644A GB9507644D0 (en) | 1995-04-12 | 1995-04-12 | Method of processing oxide nuclear fuel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| WO1996032729A1 true WO1996032729A1 (fr) | 1996-10-17 |
Family
ID=10772980
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PCT/GB1996/000872 WO1996032729A1 (fr) | 1995-04-12 | 1996-04-09 | Procede de traitement de combustible oxyde nucleaire |
Country Status (2)
| Country | Link |
|---|---|
| GB (1) | GB9507644D0 (fr) |
| WO (1) | WO1996032729A1 (fr) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1999041752A1 (fr) * | 1998-02-11 | 1999-08-19 | British Nuclear Fuels Plc | Retraitement de combustible nucleaire |
| GB2341396A (en) * | 1998-09-11 | 2000-03-15 | Toshiba Kk | Molten salt electrolysis of nuclear waste |
| GB2352729A (en) * | 1998-09-11 | 2001-02-07 | Toshiba Kk | Molten salt electrolysis of nuclear waste including filtering |
| US6379634B1 (en) | 1996-08-02 | 2002-04-30 | British Nuclear Fuels Plc | Ionic liquids as solvents |
| RU2591215C1 (ru) * | 2015-05-06 | 2016-07-20 | Федеральное государственное бюджетное образовательное учреждение высшего профессионального образования "Российский химико-технологический университет имени Д.И. Менделеева" (РХТУ им. Д.И. Менделеева) | Способ переработки облученного ядерного топлива |
| RU2619583C1 (ru) * | 2016-09-01 | 2017-05-17 | Федеральное Государственное Унитарное Предприятие "Горно - Химический Комбинат" (Фгуп "Гхк") | Способ окислительной обработки (волоксидации) облученного ядерного топлива |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1108042A (en) * | 1964-06-10 | 1968-03-27 | Euratom | Process for reprocessing nuclear fuels |
| NL7006446A (fr) * | 1969-05-27 | 1970-12-01 | ||
| GB1226198A (fr) * | 1967-12-21 | 1971-03-24 | ||
| FR2181883A1 (fr) * | 1972-04-27 | 1973-12-07 | Agip Nucleare Spa | |
| BE815189A (fr) * | 1974-05-17 | 1974-09-16 | Procede de conditionnement de combustible nucleaire irradie |
-
1995
- 1995-04-12 GB GB9507644A patent/GB9507644D0/en active Pending
-
1996
- 1996-04-09 WO PCT/GB1996/000872 patent/WO1996032729A1/fr active Application Filing
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1108042A (en) * | 1964-06-10 | 1968-03-27 | Euratom | Process for reprocessing nuclear fuels |
| GB1226198A (fr) * | 1967-12-21 | 1971-03-24 | ||
| NL7006446A (fr) * | 1969-05-27 | 1970-12-01 | ||
| FR2181883A1 (fr) * | 1972-04-27 | 1973-12-07 | Agip Nucleare Spa | |
| BE815189A (fr) * | 1974-05-17 | 1974-09-16 | Procede de conditionnement de combustible nucleaire irradie |
Non-Patent Citations (2)
| Title |
|---|
| FUJINO ET AL.: "Reaction of Lithium and Sodium Nitrates and Carbonates with Uranium Oxides", JOURNAL OF NUCLEAR MATERIALS, vol. 116, 1983, AMSTERDAM, NL, pages 157 - 165, XP000576745 * |
| PIERCE R D ET AL: "PROGRESS IN THE PYROCHEMICAL PROCESSING OF SPENT NUCLEAR FUELS", JOM, vol. 45, no. 2, 1 February 1993 (1993-02-01), WARRENDALE US, pages 40 - 44, XP000344910 * |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6379634B1 (en) | 1996-08-02 | 2002-04-30 | British Nuclear Fuels Plc | Ionic liquids as solvents |
| WO1999041752A1 (fr) * | 1998-02-11 | 1999-08-19 | British Nuclear Fuels Plc | Retraitement de combustible nucleaire |
| GB2341396A (en) * | 1998-09-11 | 2000-03-15 | Toshiba Kk | Molten salt electrolysis of nuclear waste |
| GB2352729A (en) * | 1998-09-11 | 2001-02-07 | Toshiba Kk | Molten salt electrolysis of nuclear waste including filtering |
| GB2341396B (en) * | 1998-09-11 | 2001-05-23 | Toshiba Kk | Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same |
| US6299748B1 (en) | 1998-09-11 | 2001-10-09 | Kabushiki Kaisha Toshiba | Method and apparatus of treating waste from nuclear fuel handling facility |
| GB2352729B (en) * | 1998-09-11 | 2002-04-24 | Toshiba Kk | Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same |
| US6736951B2 (en) | 1998-09-11 | 2004-05-18 | Kabushiki Kaisha Toshiba | Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same |
| RU2591215C1 (ru) * | 2015-05-06 | 2016-07-20 | Федеральное государственное бюджетное образовательное учреждение высшего профессионального образования "Российский химико-технологический университет имени Д.И. Менделеева" (РХТУ им. Д.И. Менделеева) | Способ переработки облученного ядерного топлива |
| RU2619583C1 (ru) * | 2016-09-01 | 2017-05-17 | Федеральное Государственное Унитарное Предприятие "Горно - Химический Комбинат" (Фгуп "Гхк") | Способ окислительной обработки (волоксидации) облученного ядерного топлива |
Also Published As
| Publication number | Publication date |
|---|---|
| GB9507644D0 (en) | 1995-06-14 |
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