EP1218890A2 - Process for recycling ionic liquids - Google Patents
Process for recycling ionic liquidsInfo
- Publication number
- EP1218890A2 EP1218890A2 EP20000958764 EP00958764A EP1218890A2 EP 1218890 A2 EP1218890 A2 EP 1218890A2 EP 20000958764 EP20000958764 EP 20000958764 EP 00958764 A EP00958764 A EP 00958764A EP 1218890 A2 EP1218890 A2 EP 1218890A2
- Authority
- EP
- European Patent Office
- Prior art keywords
- ionic liquid
- product
- decomposition product
- chloride
- regenerate
- 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- Withdrawn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
- 239000002608 ionic liquid Substances 0.000 title claims abstract description 51
- 238000000034 method Methods 0.000 title claims abstract description 36
- 238000004064 recycling Methods 0.000 title description 4
- 238000000354 decomposition reaction Methods 0.000 claims abstract description 19
- 239000000203 mixture Substances 0.000 claims abstract description 14
- 239000000356 contaminant Substances 0.000 claims abstract description 12
- 238000010438 heat treatment Methods 0.000 claims abstract description 7
- 239000000376 reactant Substances 0.000 claims abstract description 3
- 239000000047 product Substances 0.000 claims description 34
- 230000004992 fission Effects 0.000 claims description 11
- NEHMKBQYUWJMIP-UHFFFAOYSA-N chloromethane Chemical compound ClC NEHMKBQYUWJMIP-UHFFFAOYSA-N 0.000 claims description 10
- HRYZWHHZPQKTII-UHFFFAOYSA-N chloroethane Chemical compound CCCl HRYZWHHZPQKTII-UHFFFAOYSA-N 0.000 claims description 8
- 229960003750 ethyl chloride Drugs 0.000 claims description 8
- 150000003839 salts Chemical class 0.000 claims description 8
- VEXZGXHMUGYJMC-UHFFFAOYSA-M Chloride anion Chemical compound [Cl-] VEXZGXHMUGYJMC-UHFFFAOYSA-M 0.000 claims description 5
- VGGSQFUCUMXWEO-UHFFFAOYSA-N Ethene Chemical compound C=C VGGSQFUCUMXWEO-UHFFFAOYSA-N 0.000 claims description 5
- 238000000926 separation method Methods 0.000 claims description 5
- VEXZGXHMUGYJMC-UHFFFAOYSA-N Hydrochloric acid Chemical compound Cl VEXZGXHMUGYJMC-UHFFFAOYSA-N 0.000 claims description 4
- 238000004821 distillation Methods 0.000 claims description 4
- IXCSERBJSXMMFS-UHFFFAOYSA-N hydrogen chloride Substances Cl.Cl IXCSERBJSXMMFS-UHFFFAOYSA-N 0.000 claims description 4
- 229910000041 hydrogen chloride Inorganic materials 0.000 claims description 4
- 238000012958 reprocessing Methods 0.000 claims description 4
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 4
- 239000002699 waste material Substances 0.000 claims description 4
- 238000005979 thermal decomposition reaction Methods 0.000 claims description 3
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 claims description 2
- 239000004327 boric acid Substances 0.000 claims description 2
- 239000006227 byproduct Substances 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-M hydroxide Chemical compound [OH-] XLYOFNOQVPJJNP-UHFFFAOYSA-M 0.000 claims description 2
- 239000003758 nuclear fuel Substances 0.000 claims description 2
- 230000008929 regeneration Effects 0.000 claims description 2
- 238000011069 regeneration method Methods 0.000 claims description 2
- 229910052770 Uranium Inorganic materials 0.000 description 3
- MWUXSHHQAYIFBG-UHFFFAOYSA-N nitrogen oxide Inorganic materials O=[N] MWUXSHHQAYIFBG-UHFFFAOYSA-N 0.000 description 3
- 238000001149 thermolysis Methods 0.000 description 3
- 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 description 3
- YSNRFLSZENCKRS-UHFFFAOYSA-M 1,3-diethylimidazol-1-ium;chloride Chemical compound [Cl-].CCN1C=C[N+](CC)=C1 YSNRFLSZENCKRS-UHFFFAOYSA-M 0.000 description 2
- IIJSFQFJZAEKHB-UHFFFAOYSA-M 1,3-dimethylimidazol-1-ium;chloride Chemical compound [Cl-].CN1C=C[N+](C)=C1 IIJSFQFJZAEKHB-UHFFFAOYSA-M 0.000 description 2
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000002485 combustion reaction Methods 0.000 description 2
- 150000001875 compounds Chemical class 0.000 description 2
- 150000004693 imidazolium salts Chemical class 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 239000000155 melt Substances 0.000 description 2
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 2
- IWDFHWZHHOSSGR-UHFFFAOYSA-N 1-ethylimidazole Chemical compound CCN1C=CN=C1 IWDFHWZHHOSSGR-UHFFFAOYSA-N 0.000 description 1
- 125000000129 anionic group Chemical group 0.000 description 1
- 239000001569 carbon dioxide Substances 0.000 description 1
- 229910002092 carbon dioxide Inorganic materials 0.000 description 1
- 125000002091 cationic group Chemical group 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 238000005868 electrolysis reaction Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000013383 initial experiment Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- VUZPPFZMUPKLLV-UHFFFAOYSA-N methane;hydrate Chemical compound C.O VUZPPFZMUPKLLV-UHFFFAOYSA-N 0.000 description 1
- 239000003960 organic solvent Substances 0.000 description 1
- 239000002244 precipitate Substances 0.000 description 1
- 238000001556 precipitation Methods 0.000 description 1
- 238000003608 radiolysis reaction Methods 0.000 description 1
- 239000002994 raw material Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 239000002904 solvent Substances 0.000 description 1
- 238000000638 solvent extraction Methods 0.000 description 1
- 238000004017 vitrification Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- 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
Abstract
A method for treating a spent ionic liquid composition includes heating the composition to form a partial decomposition product thereof. The product is separated from composition contaminants and the separated product is reacted with a reactant to regenerate the ionic liquid.
Description
PROCESS FOR RECYCLING IONIC LIQUIDS
FIELD OF THE INVENTION
This invention relates to processes for treating spent ionic liquids. Reference will be made hereinafter to ionic liquids which have been used in the reprocessing of nuclear fuels but it should be understood that the invention has application in all fields of ionic liquids technology, including applications outside the nuclear industry.
BACKGROUND OF THE INVENTION Ionic liquids free of molecular solvents were first disclosed by Hurley and Wier in a series of US patents (24446331, 2446339, 2446350). In general terms an ionic liquid is a salt, a mixtures of salts, or a mixture of components which produce a salt or salts, which melts below or just above room temperature. (As used herein, the term "salt" means an entity comprising entirely of cationic and anionic species). Such liquids are known as "ionic liquids" although this term is sometimes used for salts which melt at relatively high temperatures. In this specification, the term "ionic liquid" refers to a salt which melts at a temperature of up to 100°C.
Co-pending patent application PCT/GB99/00246 discloses a method for reprocessing spent nuclear fuel which comprises dissolving the spent fuel or constituent parts of the spent fuel in an ionic liquid to substantially separate fissile material from other components of irradiated fuel. Also disclosed is the subsequent treatment of the resulting ionic liquor, either by solvent extraction or electrochemical treatment to recover the dissolved uranium or plutonium.
In addition to fissile material spent ionic liquid also contains fission products which have been dissolved together with the uranium. Considerable effort has been focused on the development of a cost effective route for the removal of these contaminants, subsequent to the separation of the uranium from the mixture, in a form suitable for conversion into a stable waste form.
Contaminant removal may be achieved by any one or a combination of a number of different routes. Selected fission products such as plutonium can be electrochemically extracted through the application of a suitable potential. The disadvantage of this is that electrolysis is a costly process, especially when performed on an industrial scale.
Fission products may alternatively or additionally be extracted from the ionic liquid by the addition of an organic solvent. Addition of an organic species results in the precipitation of fission product compounds. The precipitate can be filtered from the ionic liquid and calcined to convert to oxide prior to a vitrification step. Cleaned ionic liquid can then be recycled to the electrorefiner.
Combustion is another option for removal of contaminants, wherein spent ionic liquid is heated to temperatures in excess of 200°C. The disadvantage of this process can be measured in economic terms: Combustion of imidazolium salts results in the production of carbon dioxide, water and a mixture of nitrogen oxides (NOJ. This means that the ionic liquid cannot be recycled and is in fact destroyed.
Since one of the most significant costs in industry will be that of the requisite raw materials, any process which helps to minimise these costs through recycling is clearly a more viable option.
STATEMENT OF INVENTION
According to the present invention there is provided a method for treating a spent ionic liquid composition comprising an ionic liquid and contaminant, the method comprising heating said ionic liquid to form a partial decomposition product thereof, separating said product from said contaminant and reacting the separated product with a reactant to regenerate said ionic liquid.
When l-methyl-3-ethylimidazolium chloride is heated under reduced pressure, the ionic liquid partially decomposes to give 1 -methylimidizole, 1-ethylirnidizole,
chloromethane and chloroethane. In the initial experiments the thermolysis products were left for two days at room temperature and re-acted to produce a mixture of 1,3- dimethylimidazolium chloride, 1 ,3-diethylimidazolium chloride, and l-methyl-3- ethylimidazolium chloride. These results are surprising because thermal decomposition was previously considered to destroy any potential for recycling of the ionic liquid. In the light of these experiments however thermal decomposition for the cleaning of ionic liquids is now an economically viable alternative.
Preferably the decomposition product is separated together with at least one other decomposition product from the contaminants. Separation is effected by volatilisation during the heating process. In one embodiment of the invention the partial decomposition product is separated from the at least one other decomposition product by distillation.
Preferably the ionic liquid is heated under reduced pressure at or below 2mmHg at a temperature ranging from 200°C to 300°C or more preferably from 220°C to 250°C.
DETAILED DESCRIPTION OF THE INVENTION
Spent ionic liquid, for example l-memyl-3-emyliπudazohum chloride, is contaminated with fission products, possibly organic radiolysis products, and will require treatment in order to recover the fission products in a form suitable for conversion into a stable waste form.
In a method according to the present invention, the ionic liquid is heated under reduced pressure to a temperature within the range of 200°C to 300°C. In a preferred embodiment l-methyl-3-ethylimidazolium is heated at a temperature from 220°C to 250°C for 2-3 hours at pressures below 2mmHg. These conditions allow for only partial decomposition of the ionic liquid and therefore the recovery of as many useful component compounds of the ionic liquid as possible. It should be understood that the conditions for partial decomposition will vary for differently substituted imidazolium salts and for different mixtures thereof .
Thermolysis of the ionic liquid results in the evolution of volatile thermolysis products. In the case of l-methyl-3-ethylimidazolium chloride these are 1- methylimidizole, 1 -ethylimidizole, chloromethane and chloroethane. Chloroethane then decomposes to hydrogen chloride and ethene.
Volatile products can be collected in a cold trap and subsequent distillation of the mixture allows for separation of the components. The most volatile components are hydrogen chloride and ethene. Hydrogen chloride can be scrubbed from the system using a hydroxide scrubber and ethene can either be bottled or burnt as a by-product.
1 -methylimidizole and 1 -ethylimidizole can be separated by distillation to allow for regeneration of the specific ionic liquid l-methyl-3-ethylimidazolium chloride. It should be understood that separation is not required for processes which operate on a mixture of l-methyl-3-ethylimidazolium chloride, 1,3-dimethylimidazolium chloride and 1,3-diethylimidazolium chloride.
If the specific ionic liquid l-methyl-3-ethylimidazolium chloride is required, separated 1 -methylimidizole is reacted with chloroethane so as to regenerate the original ionic liquid l-me yl-3-emylirnidazolium chloride. Because some chloroethane is lost through its decomposition, fresh chloroethane is added to fully regenerate the ionic liquid. 1-ethylimidazole is reacted with chloromethane to regenerate the ionic liquid l-memyl-3-emylimidazolium chloride.
In a preferred embodiment of the invention the fission product residue is calcined to convert it into a stable waste form. In an alternative embodiment fission product residue is reacted with boric acid to convert it into a suitable form for disposal.
Claims
1. A method for treating a spent ionic liquid composition comprising an ionic liquid and contaminants, the method comprising heating said ionic liquid to form a partial decomposition product thereof, separating said product from said contaminants and reacting the separated product with a reactant to regenerate said ionic liquid.
2. A method according to claim 1 wherein said partial decomposition product is separated together with at least one other decomposition product from said contaminants.
3. A method according to claim 2 or claim 3 wherein said partial decomposition product is separated from the at least one other decomposition product by distillation.
4. A method according to any of the preceding claims wherein said partial decomposition product is reacted with at least one other decomposition produced to regenerate said ionic liquid.
5. A method according to any of the preceding claims wherein said separation is effected by volatilisation during the heating process.
6. A method according to any preceding claim wherein the ionic liquid is 1- memyl-3-emylimidazolium chloride.
7. A method according to claim 6 wherein the partial decomposition product is a mixture of 1 -methylimidizole, 1 -ethylimidizole, chloromethane and chloroethane.
8. A method according to claim 7 wherein 1 -methylimidizole is reacted with chloroethane to regenerate l-methyl-3-ethyIimidazolium chloride.
9. A method according to claim 5 wherein the partial decomposition product is 1 -ethylimidizole.
10. A method according to claim 9 wherein 1-emylimidizole is reacted with chloromethane to regenerate l-methyl-3-ethylimidazolium chloride.
11. A method according to any preceding claim wherein the ionic liquid is heated under reduced pressure.
12. A method according to claim 1 1 wherein the pressure is at or below 2mmHg.
13. A method according to any preceding claim wherein the ionic liquid is heated to a temperature from 200 to 300°C.
14. A method according to claim 13 wherein the ionic liquid is heated to a temperature from 220 to 250°C.
15. A method according to any of claims 3 to 14 wherein volatile products resulting from volatilisation of the ionic liquid are collected in a cold trap.
16. A method according to any preceding claim wherein hydrogen chloride is produced by heating said ionic liquid and is scrubbed from the system using a hydroxide scrubber.
17. A method according to any preceding claim wherein ethene is produced by heating said ionic liquid.
18. A method according to claim 17 wherein said ethene is bottled or burnt as a by product.
19. A process for the reprocessing of nuclear fuel and the treatment of salt wastes contaminated with fission products, the process including a method of any preceding claim.
20. A process according to claim 19 wherein the fission product contaminant residue is separated and calcined before disposal.
21. A process according to claim 19 wherein the fission product contaminant residue is reacted with boric acid before disposal.
22. Use of thermal decomposition in the treatment of spent ionic liquids wherein the decomposition products are used in the regeneration of an ionic liquid.
23. Use according to claim 23 wherein the ionic liquid is used in the reprocessing of spent nuclear fuel.
P15693
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB9919606 | 1999-08-19 | ||
GB9919606A GB9919606D0 (en) | 1999-08-19 | 1999-08-19 | Process for recycling ionic liquids |
PCT/GB2000/003234 WO2001015175A2 (en) | 1999-08-19 | 2000-08-21 | Process for recycling ionic liquids |
Publications (1)
Publication Number | Publication Date |
---|---|
EP1218890A2 true EP1218890A2 (en) | 2002-07-03 |
Family
ID=10859412
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP20000958764 Withdrawn EP1218890A2 (en) | 1999-08-19 | 2000-08-21 | Process for recycling ionic liquids |
Country Status (6)
Country | Link |
---|---|
EP (1) | EP1218890A2 (en) |
JP (1) | JP2003507185A (en) |
CN (1) | CN1375103A (en) |
AU (1) | AU7018700A (en) |
GB (1) | GB9919606D0 (en) |
WO (1) | WO2001015175A2 (en) |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2013098056A1 (en) | 2011-12-28 | 2013-07-04 | Lanxess Deutschland Gmbh | Purification of optionally hydrogenated nitrile rubber |
US11492306B2 (en) * | 2020-09-30 | 2022-11-08 | Honeywell International Inc. | Alkylation process with thermal oxidation system |
US11578278B2 (en) | 2020-08-01 | 2023-02-14 | Honeywell International Inc. | Renewable transportation fuel process with thermal oxidation system |
US11578020B2 (en) | 2020-08-04 | 2023-02-14 | Honeywell International Inc. | Naphtha complex with thermal oxidation system |
US11780795B2 (en) | 2020-08-04 | 2023-10-10 | Honeywell International Inc. | Cumene-phenol complex with thermal oxidation system |
Families Citing this family (17)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6991718B2 (en) | 2001-11-21 | 2006-01-31 | Sachem, Inc. | Electrochemical process for producing ionic liquids |
US7053232B2 (en) | 2002-08-16 | 2006-05-30 | Sachem, Inc. | Lewis acid ionic liquids |
JP4706067B2 (en) * | 2004-12-27 | 2011-06-22 | 独立行政法人産業技術総合研究所 | Ionic liquid |
JP4652359B2 (en) * | 2007-03-09 | 2011-03-16 | 日本合成化学工業株式会社 | Decomposition treatment method of ionic liquid |
JP4753141B2 (en) * | 2007-08-01 | 2011-08-24 | 独立行政法人 日本原子力研究開発機構 | Method for dissolving and separating uranium using ionic liquid, and method for recovering uranium using the same |
US7732364B2 (en) * | 2007-12-28 | 2010-06-08 | Chevron U.S.A. Inc. | Process for ionic liquid catalyst regeneration |
KR100974890B1 (en) | 2008-04-18 | 2010-08-11 | 인하대학교 산학협력단 | A recycling process of ionic liquids using microwave irradiation |
JP4843106B2 (en) * | 2011-01-24 | 2011-12-21 | 独立行政法人日本原子力研究開発機構 | Uranium recovery method using ionic liquid |
JP5734004B2 (en) * | 2011-02-07 | 2015-06-10 | 三菱重工業株式会社 | Method and apparatus for treating plutonium-containing waste liquid |
US8673800B2 (en) * | 2012-02-14 | 2014-03-18 | Chevron U.S.A. Inc. | Hydrolysis of used ionic liquid catalyst for disposal |
US9561499B2 (en) | 2013-04-19 | 2017-02-07 | Reliance Industries Limited | Process for regenerating ionic compound |
JP2020094979A (en) | 2018-12-14 | 2020-06-18 | 日立Geニュークリア・エナジー株式会社 | Organic iodine collection apparatus and organic iodine collection method |
JP7470491B2 (en) | 2019-02-25 | 2024-04-18 | 日立Geニュークリア・エナジー株式会社 | Organic iodine remover |
JP7281393B2 (en) | 2019-12-18 | 2023-05-25 | 日立Geニュークリア・エナジー株式会社 | Organic iodine remover and organic iodine remover |
JP7373454B2 (en) | 2020-04-10 | 2023-11-02 | 日立Geニュークリア・エナジー株式会社 | Organic iodine collection device |
CN112680609B (en) * | 2020-12-14 | 2022-06-03 | 中国人民解放军63653部队 | Plutonium recovery ionic liquid extractant and method for extracting and separating plutonium from plutonium-containing waste liquid |
JP2024025247A (en) | 2022-08-10 | 2024-02-26 | 日立Geニュークリア・エナジー株式会社 | filter vent device |
Family Cites Families (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB9719551D0 (en) * | 1997-09-16 | 1997-11-19 | British Nuclear Fuels Plc | Treatment of molten salt reprocessing wastes |
GB9802852D0 (en) * | 1998-02-11 | 1998-04-08 | British Nuclear Fuels Plc | Nuclear fuel reprocessing |
-
1999
- 1999-08-19 GB GB9919606A patent/GB9919606D0/en not_active Ceased
-
2000
- 2000-08-21 CN CN00811751A patent/CN1375103A/en active Pending
- 2000-08-21 EP EP20000958764 patent/EP1218890A2/en not_active Withdrawn
- 2000-08-21 AU AU70187/00A patent/AU7018700A/en not_active Abandoned
- 2000-08-21 JP JP2001519449A patent/JP2003507185A/en active Pending
- 2000-08-21 WO PCT/GB2000/003234 patent/WO2001015175A2/en not_active Application Discontinuation
Non-Patent Citations (1)
Title |
---|
See references of WO0115175A2 * |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2013098056A1 (en) | 2011-12-28 | 2013-07-04 | Lanxess Deutschland Gmbh | Purification of optionally hydrogenated nitrile rubber |
US11578278B2 (en) | 2020-08-01 | 2023-02-14 | Honeywell International Inc. | Renewable transportation fuel process with thermal oxidation system |
US11578020B2 (en) | 2020-08-04 | 2023-02-14 | Honeywell International Inc. | Naphtha complex with thermal oxidation system |
US11780795B2 (en) | 2020-08-04 | 2023-10-10 | Honeywell International Inc. | Cumene-phenol complex with thermal oxidation system |
US11492306B2 (en) * | 2020-09-30 | 2022-11-08 | Honeywell International Inc. | Alkylation process with thermal oxidation system |
Also Published As
Publication number | Publication date |
---|---|
WO2001015175A2 (en) | 2001-03-01 |
AU7018700A (en) | 2001-03-19 |
JP2003507185A (en) | 2003-02-25 |
WO2001015175A3 (en) | 2002-02-21 |
CN1375103A (en) | 2002-10-16 |
GB9919606D0 (en) | 1999-10-20 |
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