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1. 发明授权

US4162230A Method for the recovery of actinide elements from nuclear reactor waste 失效
标题翻译：从核反应堆废物回收锕系元素的方法
公开(公告)号：US4162230A
公开(公告)日：1979-07-24
申请号：US865346
申请日：1977-12-28
申请人： E. Philip Horwitz , Walter H. Delphin , George W. Mason
发明人： E. Philip Horwitz , Walter H. Delphin , George W. Mason
IPC分类号： C22B61/00 , B01D11/04 , C01F17/00 , C01G56/00 , C22B3/32 , C22B3/38 , C22B60/02 , G21C19/46 , G21F9/00 , G21F9/06 , G21F9/04
CPC分类号： G21F9/007 , C01F17/0006 , C01G56/001 , C22B3/0024 , C22B3/0025 , C22B3/0068 , C22B60/026 , G21C19/46 , Y02P10/234 , Y02W30/883
摘要： A process for partitioning and recovering actinide values from acidic waste solutions resulting from reprocessing of irradiated nuclear fuels by adding hydroxylammonium nitrate and hydrazine to the waste solution to adjust the valence of the neptunium and plutonium values in the solution to the +4 oxidation state, thus forming a feed solution and contacting the feed solution with an extractant of dihexoxyethyl phosphoric acid in an organic diluent whereby the actinide values, most of the rare earth values and some fission product values are taken up by the extractant. Separation is achieved by contacting the loaded extractant with two aqueous strip solutions, a nitric acid solution to selectively strip the americium, curium and rare earth values and an oxalate solution of tetramethylammonium hydrogen oxalate and oxalic acid or trimethylammonium hydrogen oxalate to selectively strip the neptunium, plutonium and fission product values. Uranium values remain in the extractant and may be recovered with a phosphoric acid strip. The neptunium and plutonium values are recovered from the oxalate by adding sufficient nitric acid to destroy the complexing ability of the oxalate, forming a second feed, and contacting the second feed with a second extractant of tricaprylmethylammonium nitrate in an inert diluent whereby the neptunium and plutonium values are selectively extracted. The values are recovered from the extractant with formic acid.
摘要翻译：通过向废溶液中加入硝酸铵和肼来调节溶液中的钚和钚的价态至+4氧化态，从而将经过辐照的核燃料后处理产生的酸性废液中的锕系元素分配和回收锕系元素值，从而形成进料溶液并使进料溶液与有机稀释剂中的二己氧基乙基磷酸的萃取剂接触，由此锕系元素值，大部分稀土值和一些裂变产物值被萃取剂吸收。分离是通过使负载的萃取剂与两种含水条带溶液接触，硝酸溶液选择性地剥离ium，ium和稀土值，以及草酸四甲基铵草酸盐和草酸或三甲基草酸铵铵的草酸盐溶液来选择性地剥离，，钚和裂变产物价值。铀值保留在萃取剂中，并且可以用磷酸带回收。通过加入足够的硝酸来破坏草酸盐的络合能力，形成第二种饲料，并使第二种饲料与惰性稀释剂中的三硝酸甲基硝酸铵的第二萃取剂接触，从而从草酸盐中回收ium和钚的值，由此将ium和钚选择性地提取值。用甲酸从萃取剂中回收数值。

2. 发明授权

US4162231A Method for recovering palladium and technetium values from nuclear fuel reprocessing waste solutions 失效
标题翻译：从核燃料后处理废液中回收钯和锝的方法
公开(公告)号：US4162231A
公开(公告)日：1979-07-24
申请号：US865347
申请日：1977-12-28
申请人： E. Philip Horwitz , Walter H. Delphin
发明人： E. Philip Horwitz , Walter H. Delphin
IPC分类号： B01D11/04 , C01G55/00 , C22B3/28 , C22B61/00 , G21F9/00 , G21F9/06 , G21F9/04
CPC分类号： C22B61/00 , C01G55/001 , C22B3/0016 , Y02P10/234
摘要： A method for recovering palladium and technetium values from nuclear fuel reprocessing waste solutions containing these and other values by contacting the waste solution with an extractant of tricaprylmethylammonium nitrate in an inert hydrocarbon diluent which extracts the palladium and technetium values from the waste solution. The palladium and technetium values are recovered from the extractant and from any other coextracted values with a strong nitric acid strip solution.
摘要翻译：通过将废溶液与硝酸三苯甲基铵的萃取剂在惰性烃稀释剂中接触，从废液中提取钯和锝的值，从含有这些和其它值的核燃料后处理废溶液中回收钯和锝值的方法。从萃取剂中回收钯和锝的值，并从强硝酸带溶液中回收任何其它共萃取值。

3. 发明授权

US06309614B1 Method for isolating and purifying 90Y From 90strontium in multi-curie quantities 失效
标题翻译：隔离和净化90Y的方法来自多圈数量的90天锶
公开(公告)号：US06309614B1
公开(公告)日：2001-10-30
申请号：US09549871
申请日：2000-04-14
申请人： E. Philip Horwitz , John J. Hines
发明人： E. Philip Horwitz , John J. Hines
IPC分类号： C01F1700
CPC分类号： G21F9/007
摘要： The invention relates to a process for separating and purifying multi-curie quantities 90Y of sufficient chemical and radiochemical purity suitable for use in medical applications without a series of 90Sr selective extraction chromatographic columns while minimizing loss of radioactive 90Sr parent and waste stream. The process includes dissolving a nitrate salt of an original 90Sr stock solution in H2O creating a strontium nitrate solution; acidifying the strontium nitrate solution containing 90Y with concentrated nitric acid; evaporating the strontium nitrate solution; filtering or centrifuging strontium nitrate solution to separate crystalline 90Sr nitrate salt from the solution; evaporating the remaining 90Y enriched supernate to dryness; dissolving the remaining 90Y enriched supernate in a strong acid; passing the solution through an yttrium selective extraction chromatographic column; rinsing the yttrium selective extraction chromatographic column with strong acid; and eluting yttrium from yttrium selective extraction column with strong acid.
摘要翻译：本发明涉及一种用于分离和纯化适合用于医疗应用的足够化学和放射化学纯度的多居里量90Y的方法，而不需要一系列90Sr选择性提取色谱柱，同时使放射性90Sr母体和废物流的损失最小化。该方法包括将原始90Sr储备溶液的硝酸盐溶解在H 2 O中，产生硝酸锶溶液; 用浓硝酸酸化含有90Y的硝酸锶溶液; 蒸发硝酸锶溶液; 过滤或离心硝酸锶溶液，从溶液中分离出结晶90Sr硝酸盐; 将剩余的90Y富集的上清液蒸发干燥; 将剩余的90Y富集的上清液溶解在强酸中; 使溶液通过钇选择性提取色谱柱; 用强酸冲洗钇选择性提取色谱柱; 并用强酸从钇选择性提取柱洗脱钇。

4. 发明授权

US5651883A Method for the chromatographic separation of cations from aqueous samples 失效
标题翻译：从水性样品中分离阳离子的方法
公开(公告)号：US5651883A
公开(公告)日：1997-07-29
申请号：US467402
申请日：1995-06-06
申请人： E. Philip Horwitz , Renato Chiarizia , Mark L. Dietz
发明人： E. Philip Horwitz , Renato Chiarizia , Mark L. Dietz
IPC分类号： B01D15/08 , B01J20/32 , G21F9/06 , G21F9/12 , G21F9/30
CPC分类号： B01D15/08 , B01D15/36 , B01J20/286 , B01J20/3092 , B01J20/3204 , B01J20/321 , B01J20/3212 , B01J20/3246 , G21F9/06 , G21F9/12 , G21F9/30 , B01J2220/54 , B01J2220/56
摘要： An extraction chromatographic material for extracting metal cations from aiquid stream. The extraction chromatographic material is prepared by adsorbing a diesterified methanediphosphonic acid on an inert particulate support.
摘要翻译：用于从液体流中提取金属阳离子的提取色谱材料。萃取色谱材料通过将二酯化甲基二膦酸吸附在惰性颗粒载体上来制备。

5. 发明授权

US4835107A Method for the concentration and separation of actinides from biological and environmental samples 失效
标题翻译：从生物和环境样品中浓缩和分离锕系元素的方法
公开(公告)号：US4835107A
公开(公告)日：1989-05-30
申请号：US921282
申请日：1986-10-21
申请人： E. Philip Horwitz , Mark L. Dietz
发明人： E. Philip Horwitz , Mark L. Dietz
IPC分类号： B01D11/04 , C01G56/00 , C22B3/38 , G21F9/00
CPC分类号： G21F9/007 , C01G56/001 , C22B3/0043 , C22B3/24 , Y02P10/234 , Y10T436/25125
摘要： A method and apparatus for the quantitative recover of actinide values from biological and environmental sample by passing appropriately prepared samples in a mineral acid solution through a separation column of a dialkyl(phenyl)-N,N-dialylcarbamoylmethylphosphine oxide dissolved in tri-n-butyl phosphate on an inert substrate which selectively extracts the actinide values. The actinide values can be eluted either as a group or individually and their presence quantitatively detected by alpha counting.
摘要翻译：通过将适当制备的样品通过溶解在三正丁基中的二烷基（苯基）-N，N-二甲酰基氨基甲酰基甲基氧化膦的分离柱，在无机酸溶液中通过适当制备的样品定量回收生物和环境样品中锕系元素值的方法和装置。磷酸盐在选择性提取锕系元素值的惰性底物上。锕系元素值可以作为一组或单独洗脱，并通过α计数定量检测其存在。

6. 发明授权

US07736610B2 Actinium radioisotope products of enhanced purity 失效
标题翻译：锕系放射性同位素产品具有增强的纯度
公开(公告)号：US07736610B2
公开(公告)日：2010-06-15
申请号：US11278522
申请日：2006-04-03
申请人： David Herbert Meikrantz , Terry Allen Todd , Troy Joseph Tranter , E. Philip Horwitz
发明人： David Herbert Meikrantz , Terry Allen Todd , Troy Joseph Tranter , E. Philip Horwitz
IPC分类号： C01G56/00
CPC分类号： C22B3/0005 , C22B30/06 , C22B60/00 , C22B60/0295 , G21G4/00 , Y02P10/234
摘要： A product includes actinium-225 (225Ac) and less than about 1 microgram (μg) of iron (Fe) per millicurie (mCi) of actinium-225. The product may have a radioisotopic purity of greater than about 99.99 atomic percent (at %) actinium-225 and daughter isotopes of actinium-225, and may be formed by a method that includes providing a radioisotope mixture solution comprising at least one of uranium-233 (233U) and thorium-229 (229Th), extracting the at least one of uranium-233 and thorium-229 into an organic phase, substantially continuously contacting the organic phase with an aqueous phase, substantially continuously extracting actinium-225 into the aqueous phase, and purifying the actinium-225 from the aqueous phase. In some embodiments, the product may include less than about 1 nanogram (ng) of iron per millicurie (mCi) of actinium-225, and may include less than about 1 microgram (μg) each of magnesium (Mg), Chromium (Cr), and manganese (Mn) per millicurie (mCi) of actinium-225.
摘要翻译：产物包括锕-225（225Ac）和小于约1微克（μg）的铁（Fe）/毫微米（mCi）的锕-225。产物可以具有大于约99.99原子百分比（at％）锕-225和锕-225的子同位素的放射性同位素纯度，并且可以通过包括提供包含铀-225中的至少一种的放射性同位素混合物溶液的方法形成， 233（233U）和钍-229（229Th），将铀-233和钍-229中的至少一种萃取到有机相中，基本上连续地将有机相与水相接触，基本上连续地将锕-225萃取到含水并从水相中纯化锕-225。在一些实施方案中，产物可以包含小于约1纳克（ng）的铁/锕-225的每毫里（mCi），并且可以包括小于约1微克（μg）的镁（Mg），铬（Cr），和锕-225的锰（Mn）/毫里（mCi）。

7. 发明授权

US07597862B2 Process for radioisotope recovery and system for implementing same 失效
标题翻译：放射性同位素恢复过程及其实施制度
公开(公告)号：US07597862B2
公开(公告)日：2009-10-06
申请号：US11533592
申请日：2006-09-20
申请人： David H. Meikrantz , Terry A. Todd , Troy J. Tranter , E. Philip Horwitz
发明人： David H. Meikrantz , Terry A. Todd , Troy J. Tranter , E. Philip Horwitz
IPC分类号： C01F15/00
CPC分类号： C22B3/0005 , C22B30/06 , C22B60/00 , C22B60/0295 , G21G4/00 , Y02P10/234
摘要： A method of recovering daughter isotopes from a radioisotope mixture. The method comprises providing a radioisotope mixture solution comprising at least one parent isotope. The at least one parent isotope is extracted into an organic phase, which comprises an extractant and a solvent. The organic phase is substantially continuously contacted with an aqueous phase to extract at least one daughter isotope into the aqueous phase. The aqueous phase is separated from the organic phase, such as by using an annular centrifugal contactor. The at least one daughter isotope is purified from the aqueous phase, such as by ion exchange chromatography or extraction chromatography. The at least one daughter isotope may include actinium-225, radium-225, bismuth-213, or mixtures thereof. A liquid-liquid extraction system for recovering at least one daughter isotope from a source material is also disclosed.
摘要翻译：从放射性同位素混合物中回收子代同位素的方法。该方法包括提供包含至少一种亲同位素的放射性同位素混合物溶液。将至少一种母体同位素萃取到有机相，其包含萃取剂和溶剂。有机相与水相基本上连续接触，以将至少一个子同位素萃取到水相中。水相与有机相分离，例如通过使用环形离心接触器。从水相中纯化至少一个子同位素，例如通过离子交换层析或萃取层析。至少一个子体同位素可以包括锕-225，镭-225，铋-213，或其混合物。还公开了一种用于从源材料回收至少一个子同位素的液体 - 液体萃取系统。

8. 发明授权

US07553461B2 Multivalent metal ion extraction using diglycolamide-coated particles 有权
标题翻译：使用二甘醇二酰胺包被颗粒的多价金属离子提取
公开(公告)号：US07553461B2
公开(公告)日：2009-06-30
申请号：US11619016
申请日：2007-01-02
申请人： E. Philip Horwitz , Richard E. Barrans, Jr. , Andrew H. Bond
发明人： E. Philip Horwitz , Richard E. Barrans, Jr. , Andrew H. Bond
IPC分类号： B01D15/08
CPC分类号： B01D15/3804 , B01J20/28097 , B01J20/286 , B01J20/3204 , B01J20/3208 , B01J20/3244 , B01J20/3251 , B01J2220/54 , B01J2220/58 , B01J2220/64 , C22B60/00 , C22B60/02 , C22B60/0265 , C22B60/0295 , G21F9/125 , G21G1/0005 , G21G4/08 , G21G2001/0089
摘要： A separation medium, a method for using that separation medium and an apparatus for selectively extracting multivalent cations such as pseudo-lanthanide, prelanthanide, lanthanide, preactinide or actinide cations from an aqueous acidic sample solution is described. The separation medium is preferably free-flowing and comprises particles having a diglycolamide (DGA) extractant dispersed onto an inert, porous support.
摘要翻译：描述了分离介质，使用该分离介质的方法和用于从酸性样品溶液水溶液中选择性地提取诸如假镧系元素，前镧系元素，镧系元素，脯氨酸内酯或锕系阳离子等多价阳离子的设备。分离介质优选是自由流动的，并且包括分散在惰性多孔载体上的具有二甘醇二胺（DGA）萃取剂的颗粒。

9. 发明授权

US07091338B2 Purification of 4,4′(5′)- di-t-butylcyclohexano-18-crown-6 失效
公开(公告)号：US07091338B2
公开(公告)日：2006-08-15
申请号：US10284968
申请日：2002-10-31
申请人： Andrew H. Bond , Richard E. Barrans, Jr. , E. Philip Horwitz
发明人： Andrew H. Bond , Richard E. Barrans, Jr. , E. Philip Horwitz
IPC分类号： C07B47/00 , C07D321/12 , C07C321/00 , B01D15/08 , B01D39/00
CPC分类号： C07D323/00
摘要： A purification method is disclosed for a predetermined water-insoluble extractant present in a liquid phase composition that additionally contains one or more additional extractants, synthesis reaction starting materials, and reaction byproducts dissolved as solutes in an organic diluent. An ion-containing compound is admixed with the composition to form an extractant/ion complex in the organic diluent phase that has an affinity for a new phase that is greater than the affinity for the first-named phase. The predetermined extractant/ion complex is separated from the diluent by using the new phase affinity, and the extractant/ion complex is preferably although not necessarily recovered. The extractant/ion complex is separated into extractant and ion. The extractant is recovered. Exemplary extractants include polyethers, crown ethers, crown thioethers, calixarenes, polyamines, cryptands, porphyrins and the like.

10. 发明授权

US06852296B2 Production of ultrapure bismuth-213 for use in therapeutic nuclear medicine 有权
标题翻译：生产用于治疗性核医学的超纯铋-213
公开(公告)号：US06852296B2
公开(公告)日：2005-02-08
申请号：US10159003
申请日：2002-05-31
申请人： Andrew H. Bond , E. Philip Horwitz
发明人： Andrew H. Bond , E. Philip Horwitz
IPC分类号： B01D15/26 , B01D15/36 , B01J39/04 , G01N30/08 , G01N30/46 , G01N30/88 , G21G4/08 , C01G29/00 , C22B30/00
CPC分类号： G01N30/88 , B01D15/265 , B01D15/362 , B01J39/04 , G01N30/468 , G01N2030/085 , G01N2030/77 , G01N2030/8804 , G01N2030/8868 , G21G1/0005 , G21G4/08 , Y10S423/07
摘要： A multicolumn selectivity inversion generator has been developed in which bismuth-213 is selectively extracted from an HCl solution of the actinium-225 parent (and its radiogenic descendents) by a primary separation column containing a separation medium containing a neutral oxygenated organophosphorus extractant. After rinsing with dilute HCl, the bismuth-213 is stripped with a buffered NaCl solution. The stripped solution is passed through a cation-exchange resin guard column that retains the actinium-225 and radium-225 contaminants while the bismuth-213 elutes. This generator method minimizes the unpredictable effects of radiation damage to the support material and permits the reliable production of bismuth-213 of high chemical and radionuclidic purity.
摘要翻译：已经开发了多列选择性反转发生器，其中通过含有含有中性含氧有机磷萃取剂的分离介质的初级分离柱从锕-225亲本（及其放射性后代）的HCl溶液中选择性提取铋-213。用稀HCl冲洗后，用缓冲的NaCl溶液汽提铋-213。剥离的溶液通过阳离子交换树脂保护柱，其保留锕-225和镭-225污染物，而铋-213洗脱。该发生器方法可最大限度地减少对支撑材料的辐射损伤的不可预测的影响，并允许可靠地生产高化学和放射性核素纯度的铋-213。

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