-
公开(公告)号:US12002595B2
公开(公告)日:2024-06-04
申请号:US16365132
申请日:2019-03-26
摘要: Provided herein are separation processes for metal ions present in aqueous solutions based on methods involving liquid-liquid extraction. The separation process involves a chelator that can selectively bind to at least one of the metals at a relatively low pH. This can be used, for example, for recovery and purification of actinides from lanthanides, separation of metal ions based on their valence, and separation of metal ions based on the pH of the extraction conditions.
-
2.
公开(公告)号:US20240079157A1
公开(公告)日:2024-03-07
申请号:US18458241
申请日:2023-08-30
申请人: COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES , CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIQUE , Université de Montpellier , École nationale supérieure de chimie de Montpellier
发明人: Daniel Meyer , Muriel Bertrand , Damien Bourgeois , Julie Durain
IPC分类号: G21F9/12
CPC分类号: G21F9/125
摘要: A method for stripping U(VI) and an An(IV) from an organic solution including tri-n-butyl phosphate in an organic diluent, the solution containing U(VI) and the An(IV) present as U(VI) nitrate and An(IV) nitrate at concentrations such that the U(VI) nitrate concentration is higher than the An(IV) nitrate concentration, and the sum of the U(VI) nitrate and An(IV) nitrate concentrations is ≥55 g/L. The method includes contacting the organic solution and an aqueous solution of nitric and oxalic acids, the oxalic acid concentration in the aqueous solution and the O/A volume ratio selected so that the oxalic acid is deficient with respect to the stoichiometric conditions of a complete precipitation of U(VI) and actinide(IV), to obtain a precipitate containing the actinide(IV) in oxalate form and a fraction of the U(VI) in oxalate form with a U(VI)/actinide(IV) mass ratio of between 0.5 and 5; and separating the precipitate from the organic and aqueous solutions.
-
公开(公告)号:US20230382769A1
公开(公告)日:2023-11-30
申请号:US17826956
申请日:2022-05-27
发明人: JAKE W. AMOROSO , KYLE S. BRINKMAN , JIANHUA TONG , JUN GAO , YUQING MENG , JAMES M. BECNEL
CPC分类号: C02F1/281 , B01D71/0271 , B01D15/203 , B01D15/1885 , B01D15/1807 , C02F1/44 , G21F9/12 , C02F2303/16
摘要: Methods and systems directed to the separation of a heavy hydrogen isotope, e.g., tritium, from an aqueous stream are described. The methods and systems incorporate a separation media that includes a proton conducting ceramic that at low temperatures preferentially adsorbs heavy hydrogen isotopes and at high temperature preferentially adsorbs lighter heavy hydrogen isotopes. The methods can be temperature controlled to sequentially purify a contaminated stream and regenerate the separation media. The separation media can be free of traditional hydrogen isotope exchange catalyst materials.
-
公开(公告)号:US11807549B2
公开(公告)日:2023-11-07
申请号:US16534764
申请日:2019-08-07
发明人: John Raymont , James Fredrickson , Joshua Leighton Mertz , David Carlson , Mark Denton , Gary Hofferber , Ja-Kael Luey , Zechariah James Fitzgerald , Ronald Merritt Orme , Eric Vincent Penland
IPC分类号: C02F9/00 , C02F1/00 , G21F9/04 , G21F9/12 , C02F9/20 , C02F1/28 , C02F101/00 , C02F1/42 , C02F1/44
CPC分类号: C02F9/00 , C02F1/001 , C02F1/008 , C02F1/28 , C02F9/20 , G21F9/04 , G21F9/12 , B01D2311/25 , B01D2311/251 , C02F1/281 , C02F1/42 , C02F1/441 , C02F1/444 , C02F2101/006 , C02F2201/005 , C02F2201/007 , C02F2201/008 , C02F2209/001 , C02F2209/003 , C02F2209/005 , C02F2209/05 , C02F2209/40 , C02F2301/046 , C02F2301/08 , Y02E30/00 , Y02E30/30 , Y02W10/37
摘要: A mobile processing system is disclosed for the removal of radioactive contaminants from nuclear process waste water. The system is fully scalable, modular, and portable allowing the system to be fully customizable according the site-specific remediation requirements. It is designed to be both transported and operated from standard sized intermodal containers or custom designed enclosures for increased mobility between sites and on-site, further increasing the speed and ease with which the system may be deployed. Additionally, the system is completely modular wherein the various different modules perform different forms or stages of waste water remediation and may be connected in parallel and/or in series. Depending on the needs of the particular site, one or more different processes may be used. In some embodiments, one or more of the same modules may be used in the same operation.
-
公开(公告)号:US20230143744A1
公开(公告)日:2023-05-11
申请号:US17793815
申请日:2021-01-20
发明人: Kazuyuki ISHII , Kyoko ENOMOTO
CPC分类号: B01J20/0259 , C02F1/288 , C02F1/281 , G21F9/12 , C01C3/12 , B01J20/0229 , B01J20/0237 , B01J20/3293 , B01J20/0274 , B01J20/0222 , B01J20/0225 , B01J20/0244 , C02F2101/20
摘要: The present invention is to provide a novel adsorbent which is low in cost, has versatility and has high adsorption ability. Specifically, the present invention is to provide an adsorbent containing a metal salt of a cyanometallic acid obtained by a reaction of a salt of a cyanometallic acid and a compound containing a metal element, wherein the reaction is carried out using the compound containing a metal element in an amount of less than 100 mol % of the theoretical amount relative to 1 mol of the salt of a cyanometallic acid, a method of producing the same, and a method for removing harmful ions from water using such an adsorbent.
-
公开(公告)号:US20230080965A1
公开(公告)日:2023-03-16
申请号:US17878068
申请日:2022-08-01
发明人: GANG WANG , Lin Zhao , Shiyong Wang
IPC分类号: B01J20/02 , C01B21/097 , B01J20/28 , B01J20/30 , G21F9/12
摘要: The invention discloses a phosphorus nitride adsorbent with high-efficiency selectivity, and its application thereof. The phosphorus nitride adsorbent has a mutually cross-linked hollow tubular structure. The adsorbent can have an adsorption capacity of 435.58 mg·g−1 and 7.01 mg·g−1 for spiked seawater and natural seawater with a uranium concentration of 350 ppb, and the adsorbent has a long service life, and can still maintain 91.14% of the initial adsorption capacity after 5 cycles of adsorption and desorption. Taking into account the advantages of a short material preparation cycle, a wide range of raw material sources, a low cost, an excellent adsorption performance, and long service life, the adsorbent can be used in technical fields such as uranium-containing wastewater treatment, uranium ore resource recovery, uranium extraction from seawater and the like.
-
公开(公告)号:US20230005634A1
公开(公告)日:2023-01-05
申请号:US17778508
申请日:2020-11-19
申请人: Victor REMEZ ALONSO
发明人: Victor REMEZ ALONSO
摘要: The invention relates to technology for processing liquid radioactive waste containing, inter alia, tritium isotopes, which are formed in various nuclear industry plants, and also during decommissioning of such plants. The technical result of the claimed invention consists in simplifying the technological procedure for processing liquid radioactive waste containing, inter alia, tritium isotopes by excluding complicated and lengthy operations associated with testing a concrete mixture produced from deactivated liquid radioactive waste, and also in increasing the ecological safety by reducing the size of areas for storage of the waste produced during the processing of the liquid radioactive waste. The claimed technical result is achieved in that a method for processing liquid radioactive waste containing, inter alia, tritium isotopes involves removing radioactive substances from the liquid radioactive waste so as to produce a low-level waste solution, and introducing a binder into the low-level waste solution produced in order to prepare a concrete mixture which complies with structural, radioecological, and sanitary and hygiene requirements, wherein components that have a negative effect on the technical characteristics of the concrete mixture being produced are removed from the low-level waste solution before the binder is added.
-
公开(公告)号:US11446631B2
公开(公告)日:2022-09-20
申请号:US16490304
申请日:2018-03-01
发明人: Takashi Sakuma , Makoto Komatsu , Takeshi Izumi , Takayasu Tanaka , Takafumi Tanaka , Hidenori Ishioka , Ayaka Ando , Tomoko Yoshimi , Nobuyuki Hashimoto , Hiroaki Uchida , Shigeru Nagaoka
摘要: Provided is a particulate alkaline earth metal ion adsorbent having a large adsorption capacity. The particulate alkaline earth metal ion adsorbent comprising: a potassium hydrogen dititanate hydrate represented by a chemical formula K2-xHxO·2TiO2·nH2O, wherein x is 0.5 or more and 1.3 or less, and n is greater than 0; and no binder, wherein the particulate alkaline earth metal ion adsorbent has a particle size range of 150 μm or more and 1000 μm or less.
-
公开(公告)号:US11446608B2
公开(公告)日:2022-09-20
申请号:US16617935
申请日:2018-05-29
发明人: Tatsuhiko Ihara , Hirokuni Yamanishi , Hiroshi Noma , Toshifumi Taira , Takashi Hoshiya , Kazuya Fujimoto
摘要: The present invention relates to a method for reducing the HTO concentration in a tritium-containing aqueous solution. The present invention includes bringing water vapor or the like of a tritium-containing aqueous solution into contact with a porous material having pores in a pore diameter range of 500 Å or less, selectively occluding the HTO in the tritium-containing aqueous solution in the porous material, and obtaining a tritium-containing aqueous solution in which the HTO concentration thereof is reduced. The present invention relates to a device used for reducing the HTO concentration in a tritium-containing aqueous solution. The present invention includes a reservoir for a raw tritium-containing aqueous solution, a means for generating water vapor or the like of the tritium-containing aqueous solution, an occlusion means in which is accommodated a porous material having pores in a pore diameter range of 500 Å or less, and a means for recovering the tritium-containing aqueous solution in which the HTO concentration is reduced. The present invention furthermore includes a transfer means for transferring the water vapor or the like to the occlusion means, and a means for transferring the tritium-containing aqueous solution in which the HTO concentration is reduced from the occlusion means to a recovery means.
-
公开(公告)号:US20220199274A1
公开(公告)日:2022-06-23
申请号:US17540332
申请日:2021-12-02
发明人: IAN L. PEGG , MIGUEL PENAFIEL
摘要: Methods and materials are described for the removal of iodate from aqueous solutions. The methods comprise reduction of the iodate to iodide and subsequent or concurrent removal of the iodide by sorption, ion exchange, or precipitation. These methods are effective for the removal of radioactive iodine from radioactive and nuclear wastes.
-
-
-
-
-
-
-
-
-