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Patent Agency Ranking
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公开(公告)号：US4191814A
公开(公告)日：1980-03-04
申请号：US927196
申请日：1978-07-24
Applicant: David R. Amick
Inventor： David R. Amick
CPC classification number: B01J41/12 , C08F8/44 , Y02P20/582
Abstract: Anion exchange resins produced by reacting a stabilized polychloromethylstyrene polymer bead with a polyamine containing at least two tertiary amine groups of which at least one is a terminal group, and processes for producing the resins in uniform sizes.
Abstract translation: 通过使稳定的聚氯甲基苯乙烯聚合物珠粒与至少两个其中至少一个末端基团的至少两个叔胺基团的多胺反应制备的阴离子交换树脂，以及用于制备均匀尺寸的树脂的方法。
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公开(公告)号：US4151079A
公开(公告)日：1979-04-24
申请号：US912618
申请日：1978-06-05
Applicant: Louis E. Horembala
Inventor： Louis E. Horembala
CPC classification number: B01J49/0021
Abstract: Problems encountered with sodium leakage after regeneration of mixed bed and ion exchange units utilized to purify boiler feed waters can be reduced or eliminated by using as the regenerant for the anion exchange resin an aqueous solution of potassium hydroxide. Likewise, in the regeneration of cation condensate polishing units utilized to purify boiler feed waters, sodium leakage can be reduced or eliminated by utilizing a potassium salt as the regenerant.Additionally, potassium salts of various inorganic reducing agents can also be utilized to remove iron from ion exchange systems operated in the above manner.
Abstract translation: 通过使用氢氧化钾水溶液作为阴离子交换树脂的再生剂，可以减少或消除用于净化锅炉给水的混合床和离子交换单元再生后的钠泄漏所遇到的问题。 同样，在用于净化锅炉给水的阳离子冷凝物研磨单元的再生中，可以通过利用钾盐作为再生剂来减少或消除钠泄漏。
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49.发明授权Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products 失效从含有中子辐射的可裂变材料和裂变产物的基质中回收钼-99的方法
公开(公告)号：US4094953A
公开(公告)日：1978-06-13
申请号：US777627
申请日：1977-03-14
Applicant: Ali Sameh Abdel Hadi , Johann Reinhardt , Jutta Knapp
Inventor： Ali Sameh Abdel Hadi , Johann Reinhardt , Jutta Knapp
CPC classification number: G21F9/007
Abstract: Process for recovering molybdenum-99 from a matrix which has been irradiated with neutrons and contains fissionable materials and fission products, wherein the matrix is decomposed in an aqueous alkali hydroxide solution and the molybdenum-99 and part of the fission products are dissolved, the solution containing the molybdenum-99 is separated from a residue of particles containing at least actinides and lanthanides and is treated with thiocyanate ions to form a molybdenum complex. In the process, the alkali solution containing molybdenum in the form of molybdenum (MoO.sub.4.sup. --) is conditioned with an iodine reduction agent. Mineral acid is added to the alkali solution. The molybdenum contained in the acidfied solution is reduced to form three-valent molybdenum Mo(III) and the Mo(III) is complexed with SCN.sup.- ions to form [Mo(SCN).sub.6 ].sup.3- ions. The [Mo(SCN).sub.6 ].sup.3- ion containing solution is treated with a previously-conditioned, organic ion exchanger to selectively sorp the molybdenum. The ion exchanger, which is now charged with molybdenum, is separated from the solution which is now free of molybdenum. The separated molybdenum charged ion exchanger is washed with a wash solution in order to remove residual quantities of the molybdenum free solution. The molybdenum from the washed ion exchanger is eluted with a liquor at an elution temperature in the range from about 20.degree. C to about 70.degree. C.BACKGROUND OF THE INVENTIONThe present invention relates to a process for the recovery of molybdenum-99 from a matrix containing neutron irradiated, fissionable materials and fission products, in which the matrix is decomposed in an aqueous alkali hydroxide solution and the molybdenum-99 and part of the fission products are dissolved, the solution containing the molybdenum-99 is separated from a residue of solid particles containing at least actinides and lanthanides and is treated with thiocyanate ions in order to form a molybdenum-99 complex.In nuclear medicine, the significance of Tc-99 is continuously at an increase as an indicator in the diagnosis of tumors. Since, however, technitium has a relatively short halflife (T.sub.1/2 = 6.0 h), the mother nuclide Mo-99 is eluted when required. Thus, a technitium generator is used to provide the technitium. The technitium generators generally comprise a chromatographic column having Mo-99 bearing molybdate ion absorbed thereon. Radioactive decay of the relatively, long-lived Mo-99 produces Tc-99. Elution of the chromatographic column provides an on-the-spot source of the technitium.Previously, natural molybdenum which had been activated in reactors was used in the generators to produce the technitium. The drawbacks of this natural molybdenum material are that large columns are required for small specific activities, large injection volumes are required in order to retain the required activity, and there is a very limited availability of the generator due to the low activity.Fission molybdenum has been found to be useful in technitium generators to produce the technitium and has been used to a greater degree in recent times. This, however, requires much refined processing technology in order to obtain the required degree of molybdenum purity. The required radionuclide purity of the fission molybdenum for use in a technitium generator is:.gamma. :I-131
Abstract translation: 从已经用中子照射并含有可裂变材料和裂变产物的基质中回收钼-99的方法，其中基质在碱金属氢氧化物水溶液中分解，钼-99和部分裂变产物溶解， 含有钼-99的物质与至少含有锕系元素和镧系元素的颗粒的残留物分离，并用硫氰酸根离子处理以形成钼络合物。 在此过程中，含有钼（MoO4 - ）形式的钼的碱溶液用碘还原剂调理。 将矿物酸加入碱溶液中。 含钼
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公开(公告)号：US3995009A
公开(公告)日：1976-11-30
申请号：US613704
申请日：1975-09-15
Applicant: Karl J. Notz
Inventor： Karl J. Notz
CPC classification number: B01J39/046 , C01G43/00 , C22B3/42 , C22B60/0265 , Y02P10/234
Abstract: A method for loading ion exchange resins is described. The process comprises contacting a weak acid cation exchange resin in the ammonium form with a uranyl fluoride salt solution.
Abstract translation: 描述了负载离子交换树脂的方法。 该方法包括使铵形式的弱酸阳离子交换树脂与氟化铀盐溶液接触。
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