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    • 1. 发明授权
    • Process for recovering molybdenum-99 from a matrix containing neutron
irradiated fissionable materials and fission products
    • 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
    • US4094953A
    • 1978-06-13
    • US777627
    • 1977-03-14
    • Ali Sameh Abdel HadiJohann ReinhardtJutta Knapp
    • Ali Sameh Abdel HadiJohann ReinhardtJutta Knapp
    • G21F9/00B01J1/08
    • G21F9/007
    • 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
    • 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
    • 3. 发明授权
    • Process for recovering molybdenum-99 from a matrix containing neutron
irradiated fissionable materials and fission products
    • 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
    • US4093697A
    • 1978-06-06
    • US777626
    • 1977-03-14
    • Ali Sameh Abdel HadiPeter-Michael MenzlerJohann Reinhardt
    • Ali Sameh Abdel HadiPeter-Michael MenzlerJohann Reinhardt
    • C01C3/20G21F9/00C01G39/00
    • C01C3/20G21F9/007
    • 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 molybdate (MoO.sub.4.sup.--) is conditioned with an iodine reduction agent. Mineral acid is added to the alkali solution. The molybdenum contained in the acidified 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 acid solution which contains [Mo (SCN).sub.6 ].sup.3- ions and contaminants is brought into contact with previously conditioned di-sec butyl ether (organic phase). The molybdenum thiocyanate complex ions are selectively extracted from the aqueous phase into the organic phase whereby the contaminants remain practically completely in the aqueous phase. The organic phase which is now charged with the [Mo(SCN).sub.6 ].sup.3- ions is separated from the molybdenum free solution. The separated organic phase is washed with diluted mineral acid in a concentration in the range from 0.001 to 0.1 Mol/l in a quantity corresponding approximately to the volume of the organic phase. The molybdenum is re-extracted with mineral acid in a concentration in the range from 5 Mol/l to 11 Mol/l from the washed organic phase into an aqueous phase.
    • 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,将含有钼酸盐(MoO 4 - )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。 酸化溶液中所含的钼被还原形成三价钼Mo(III),Mo(III)与SCN-离子络合形成[Mo(SCN)6] 3-离子。 含有[Mo(SCN)6] 3-离子和污染物的酸溶液与先前调节的二仲丁基醚(有机相)接触。 将硫氰酸钼络合物离子从水相中选择性地萃取到有机相中,使得污染物在水相中几乎完全残留。 现在带有[Mo(SCN)6] 3-离子的有机相与无钼溶液分离。 分离的有机相用浓度在0.001至0.1Mol / l范围内的稀释的无机酸洗涤,其量相当于有机相的体积。 将钼从浓度为5Mol / l至11Mol / l的无机酸从洗涤的有机相再萃取到水相中。