生产99Mo、131I和89Sr医用同位素的水溶液堆

99Mo1、31I和89Sr等医用同位素对人类健康和医学的发展具有非常重要的作用。与靶辐照反应堆相比,用水溶液堆生产99Mo1、31I和89Sr具有安全性好,结构简单,经济价值高,无靶件制备、溶解工艺,产生废物少等优点,用水溶液堆生产医用同位素具有很好的发展前景。由于多堆芯水溶液堆、高功率水溶液堆均能显著提高产率,低富集度235U水溶液堆符合核不扩散条约中对235U浓缩度的要求,因此这三种堆是水溶液堆未来的发展方向。     

氢氧化镁共沉淀法测定海水中纳摩尔级活性磷酸盐

利用海水中Mg(2+)与OH-生成沉淀时会共沉淀PO(3-4)的特性,富集海水中PO(3-4),富集后的Mg(OH)2沉淀用酸溶解,应用磷钼蓝-分光光度法测定.对试剂用量、离心速度及时间、Mg(OH)2,溶解用酸种类、H/Mo等实验参数和条件进行了优化.并采用与常规磷钼蓝法介质一致的H2SO4作为Mg(OH)2沉淀溶解...     

负载型杂多蓝HPB/SiO_2的制备、表征与催化性能研究

用化学还原与共沉淀法制备了负载型杂多蓝催化剂H4PW6Mo5MovO40·27H2O／SiO2（简记HPB／SiO2）,并用ICP、IR、吡啶吸附IR光谱及TG－DTA等进行了表征．将该催化剂应用于乙酸丁酯的合成反应,结果表明,该催化剂有Bronsted酸位与Lewis酸位和热稳定性,在最佳催化条件下,乙酸丁酯的收率可达98．3％,醋酸的转化率大于99％,并可重复使用10次以上．     

铋钼复合氧化物表面上激光促进异丁烷选择氧化制甲基丙烯酸

 用共沉淀法制备了Bi和Mo的复合氧化物固体材料．运用XRD,IR,TPD和激光促进表面反应（LSSR）技术研究了其晶体结构、表面构造、化学吸附特性和激光促进异丁烷选择氧化反应性能．结果表明：Bi－Mo－O复合氧化物含有α－Bi2Mo3O12和少量γ－Bi2MoO6晶相;其表面上存在着Lewis碱位（MoO和Mo—O—Bi键中的O）及Lewis酸位（Bi3＋）;异丁烷的两个甲基H分别吸附在两个相邻的Lewis碱位MoO上,形成双位分子吸附态;在常压和200℃条件下,用一定频率的激光激发MoO键1000次,异丁烷的转化率可达11．2％,其反应产物是异丁烯、甲基丙烯醛和甲基丙烯酸,其中甲基丙烯酸的选择性为90％．根据实验结果,探讨了激光促进异丁烷选择氧化为甲基丙烯酸的表面反应机理．     

饿钼复合氧化物表面上激光促进异丁烷选择氧化制甲基丙烯酸

用共沉淀法制备了Bi和Mo的复合氧化物固体材料,运用XRD,IR,TPD和激光促进表面反应（LSSR）技术研究了其晶体结构、表面构造、化学吸附特性和激光促进异丁烷选择氧化反应性能,结果表明：Bi-Mo-O复合氧化物含有α-Bi2Mo3O12和少量γ-Bi2MoO6晶相;其表面上存在着Lewis碱位（Mo=O和Mo-O-Bi键中的O)及Lewis酸位（Bi^3 );异丁烷的两个甲基H分别吸附在两个相邻的Lewis碱位Mo=O上,形成双位分子吸附态;在常压和200℃条件下,用一定的激光激发Mo=O键1000次,异丁烷的转化率可达11.2％,其反应产物是异丁烯、甲基丙烯醛和甲基丙烯酸,其中甲基丙烯酸的选择性为90％,根据实验结果,探讨了激光促进异丁烷选择氧化为甲基丙烯酸的表面反应机理。     

纳米级MoO3微粉的制备与性质

以(NH4)6Mo7O24·4H2O和HAc为原料,制备了纳米级MoO3微粉,用电镜观察其形貌和粒径的大小,并进行X射线衍射分析.在制备过程中,通过严格控制溶液的浓度、酸度等条件,首先得到纤维状的酸式仲钼酸铵(NH4)4H2Mo7O24·4H2O和 (NH4)3H3Mo7O24·4H2O.并通过加热使其分解,从而获得纳米级MoO3微粉.     

具有Dawson结构的钼钒磷杂多酸的制备和性质研究

本文报道用改良的分步处理合成方法, 直接制备了五种未见报道的2:18系列钼钒磷杂多酸, 详细考察了它们的生成条件. 经元素分析、电位滴定和差热热重分析确定阴离子的组成分别为[P2Mo17VO62]^7^-,[P2Mo16V2O62]^8^-,[P2Mo15V3O62]^9^-, [P2Mo14V4O62H2]^8^-, [P2Mo13V5O62H2]^9^-. 对五种杂多酸的热化学性质和碱度进行了讨论. 根据紫外、红外及X射线衍射结果讨论了它们的结构, 表明都属于具有Dawson结构的杂多化合物.     

Mo对猝冷Ni-Mo骨架催化剂结构和催化性能的影响

采用猝冷法制备了不同Mo含量的Ni-Mo-Al合金,经碱处理活化后得到猝冷Ni-Mo骨架催化剂．以ICP,N2物理吸附,XRD,H2-TPD等手段对合金及催化剂的物化性质进行了表征．结果表明,随着Mo含量的增加,合金中依次出现Ni16Mo10Al74,MoAl3物相,同时NiAl3相减少,Ni2Al3相增加．Mo的存在使合金中更多的铝被抽提,减少了催化剂中残留的Ni2Al3物相,催化剂的比表面积、平均孔径、孔容和晶粒尺寸均随Mo含量增加而减小．将催化剂用于2-乙基蒽醌加氢反应,发现Mo加快了反应速率,同时抑制了降解产物的产生．在催化剂中Mo含量达到2．47wt％时,双氧水的得率可达到100％．结合M晶粒大小、表面吸附氢状态、Mo的化学态,进一步讨论了Mo对猝冷Ni-Mo骨架催化件能的修饰作用．     

乙烷部分氧化超细Fe－Mo－O催化剂的研究

采用溶胶-凝胶法制备了Fe－Mo－O催化剂，用XRD、TEM、BET、IR、TPR、TPD和微反等技术研究了催化剂晶体结构、表面构造、晶格氧活泼性、化学吸附和乙烷部分氧化反应性能。Fe－Mo－O复合氧化物催化剂是由超细微粒组成，微粒粒径约10 nm～20 nm，比表面积为48.1 m2/g。催化剂表面由Lewis碱位（Mo=O键的端氧和Fe－O－Mo键中的桥氧）及Lewis酸位构成。乙烷能以甲基中的H原子吸附在催化剂表面Lewis碱位Mo=O的端氧上形成分子吸附态，其部分氧化产物主要是C2H4和少量的CH3CHO。     

离子交换法制备医用无载体核素~(199)Au

本文研究了用离子交换法从热中子辐照的铂靶制备医用无载体核素~(1999)Au。将溶靶后的Pt—~(199)Au溶液(6mol/L HCl)通过阳离子交换树脂柱后,用6mol/L HCl(Cl_2)溶液洗出Pt;再用丙酮,洗出~(199)Au使Pt—~(199)Au,得到分离。获得的~(199)Au的放射性纯度用8192道r谱仪进行了鉴定。     

Radiochemical separation of99Mo from natural uranium irradiated with thermal neutrons

⁹⁹Mo was separated from uranium and insoluble fission product hydroxides. More than 98% of⁹⁹Mo radioactivity was extracted with bis (2-ethylhexyl)phosphoric acid. The organic phase was washed and⁹⁹Mo was back-extracted from the organic phase with NH₄OH solution. The percent recovery from the organic phase was 91% and the purity of⁹⁹Mo was more than 99%. Pure^99mTc was also extracted from the organic phase with a saline solution. Reversed-phase partition chromatography was used for the purification of⁹⁹Mo from¹³¹I and other fission products (10% HDEHP on kieselguhr bed).¹³¹I and other isotopes were quantitatively eluted with 0.1M H₂SO₄,⁹⁹Mo was eluted using a mixture of 0.5 M HCl and 30% H₂O₂.     

Feasibility study for production of 99mTc by neutron irradiation of MoO3 in a 250 kW TRIGA Mark II reactor

The subject of this paper is to explore the possibility to obtain ^99mTc from activation of ⁹⁸Mo, using the TRIGA Mark II low flux research reactor (Vienna, Austria). Irradiation of both natural and enriched in ⁹⁸Mo molybdenum oxides was compared. Aims of this work included the determination of neutron fluxes and ⁹⁸Mo(n, γ)⁹⁹Mo reaction effective cross section in the TRIGA Mark II reactor irradiation channels, calculation of ⁹⁹Mo specific activities, determination of optimal irradiation conditions for the subsequent ^99mTc separation from MoO₃ targets using concentrating technologies.     

99mTc generator with hydrated MnO2 as adsorbent of 99Mo

An ^99mTc generator with MnO₂ as adsorbent of ⁹⁹Mo was investigated. Through batch experiments the retention of ⁹⁹Mo onto MnO₂was studied as a function of the shaking time and the pH value of the ⁹⁹Mo solution. It was found that ⁹⁹Mo showed a retention of 100% onto MnO₂ at the pH range from 3 to 11, and the equilibrium distribution was reached in less than 10 minutes. In column experiments the retention of ⁹⁹Mo onto MnO₂ was also high: 99.72%. In this case, the pH of the utilized ⁹⁹Mo solution was 5. The ^99mTc could be eluted from the MnO₂-⁹⁹Mo column by using either distilled water with a pH of 5 or an aqueous solution of 0.9% NaCl. With the saline solution, the ^99mTc elution yields were higher than 80%, and only one aliquot of 5 ml was needed to get these yields. The best results were obtained when the column was packed with 1 g of MnO₂. The water and the saline solution were passed through the column at a rate of 1.25 ml/min.     

Separation of molybdenum and technetium on DI-2-ethylhexylphosphoric acid (D-2-EHPA)-kieselguhr

The distribution ratio of Mo(VI) and Tc(VII) in different acid media on D-2-EHPA-kieselguhr was studied in batch experiments. From these data a separation procedure for Mo-Tc is proposed, which consists in the selective elution of Tc(VII) and Mo(VI) by reverse-phase partition chromatography. The D-2-EHPA-kieselguhr column can also be used as a solid phase for a(99m)Tc generator.     

<Superscript>99</Superscript>Mo/<Superscript>99m</Superscript>Tc generators based on aluminum molybdate gel matrix prepared by nano method

A procedure for preparation of ⁹⁹Mo/^99mTc radioisotope generator based on low specific activity neutron activated ⁹⁹Mo was developed. Aluminum molybdate(VI)-⁹⁹Mo of high Mo(VI) content (~?364 mg/g Al⁹⁹Mo) was prepared by mixing low specific activity molybdate(VI)-⁹⁹Mo and aluminum mixture solution with isoamyl alcohol. Al⁹⁹Mo gel matrix was precipitated when the pH of the mixture solution was raised to ~?5 by addition of NaOH to the mixture. Radiometric measurements indicate the strong fixation of Molybdate(VI)-⁹⁹Mo species in the form of the sparingly insoluble Al⁹⁹Mo gel matrix. The prepared AlMo gel matrix was physiochemically characterized. Al⁹⁹Mo gel matrix was used as a base material for preparation of ⁹⁹Mo/^99mTc generator. The ^99mTc eluted from ⁹⁹Mo/^99mTc radioisotope generator was found to have relatively high elution yield (84?±?2.3%), radionuclidic (≥?99.99%), radiochemical (98.1?±?0.9%) and chemical purity.     

Determination of calibration curves for <Superscript>131</Superscript>I in thyroid tumour metabolic radiotherapy and other radionuclides used in SPECT imaging

Large columns containing aluminum oxide (Al₂O₃) or gel (e.g. zirconium molybdate) are needed to prepare ⁹⁸Mo(n,γ)⁹⁹Mo→^99mTc column chromatographic generators that results in large elution volumes containing relatively high ⁹⁹Mo impurity and low concentrations of ^99mTc. The decrease in radioactive concentration or specific volume concentration of ^99mTc places a limitation on some pharmaceutical kits (DTPA, MIBI, ECD, etc.) or clinical procedures. We report on the post elution concentration of ^99mTc using in house prepared lead cation-exchange and alumina columns. Using these columns high bolus volumes (10–60 mL 0.02M sodium sulfate) of ^99mTc can conveniently be concentrated in 1 mL of physiological saline. This approach also works very effectively to prepare high specific volume solutions of ^99mTc-pertechnetate from a fission based ⁹⁹Mo/^99mTc generator in the second week of its normal working life.     

Solid targets for 99mTc production on medical cyclotrons

Recent disruptions in the molybdenum-technetium generator supply chain prompted a review of non-reactor based production methods for both ⁹⁹Mo and ^99mTc. Small medical cyclotrons (E _p ~ 16–24 MeV) are capable of producing Curie quantities of ^99mTc from isotopically enriched ¹⁰⁰Mo using the ¹⁰⁰Mo(p,2n)^99mTc reaction. Unlike most other metallic target materials for routine production of medical radioisotopes, molybdenum cannot be deposited by reductive electroplating from aqueous salt solutions. To overcome this issue, we developed a new process for solid molybdenum targets based on the electrophoretic deposition of fine ¹⁰⁰Mo powder onto a tantalum plate, followed by high temperature sintering. The targets obtained were mechanically robust and thermally stable when irradiated with protons at high power density.     

Separation of99mTc from neutron-irradiated MoO3 by precipitation as CaMoO4

A method is discussed for separating^99mTc from⁹⁹Mo by dissolution and reprecipitation of CaMoO₄ containing⁹⁹Mo-^99mTc.^99mTc can be obtained successfully with a yield of about 80% and with a radionuclidic purity as high as over 99.7%. On the other hand, by agitating Ca⁹⁹ MoO₄ solid with 0.9% NaCl aqueous solution,^99mTc can directly be obtained with a yield of about 30% without any impurities.     

Multi-reaction proton activation analysis for traces of molybdenum

The application of proton activation analysis to the determination of molybdenum is described. Thick molybdenum targets were bombarded with 12-MeV and 15-MeV protons. The reactions studied were ⁹²Mo(p,n)⁹² Tc, ⁹⁴Mo(p,n)^94gTc + ⁹⁵Mo(p,2n)^94gTc, ⁹⁵Mo(p,n)^95m Tc + ⁹⁶Mo(p,2n)^95mTc, ⁹⁵Mo(p,n)^95g Tc + ⁹⁶Mo(p,2n)^95gTc, ⁹⁶Mo(p,n)^96gTc+⁹⁷Mo(p,2n)^96gTc and ¹⁰⁰Mo(p,n)^99m Tc. Except for the Mo + p→^905mTc reaction, all these reactions give high analytical sensitivities. For 12-MeV protons and an irradiation time of one half-life or a maximum of 2 h, the sensitivities range from 5 · 10² to 6· 10³ d.p.m./p.p.m. μA, and for 15-MeV protons and the same irradiation conditions from 10³ to 10⁴ d.p.m./p.p.m. μA. In addition to the high sensitivity, the great advantage of proton activation is that different principal reactions yield indicator radionuclides with half-lives between 4.4 min and 61 d. Simultaneous determinations by these reactions are of value for checking the accuracy. For each reaction, detailed data are given on nuclear and instrumental interferences. Analytical application of this multi-reaction proton activation analysis is illustrated by the instrumental determination of molybdenum in cobalt.     

The quality of99mTc eluates

The possible effects of several protecting procedures on the quality of^99mTc eluates were investigated. The content of⁹⁹Mo in the eluates (⁹⁹Mo breakthrough) was expressed in (%) with respect to the total adsorbed⁹⁹Mo radioactivity and in () i.e. as the ratio of⁹⁹Mo and^99mTc radioactivities in each particular eluate. The radiochemical purity was expressed in (%) of^99mTc(VII) in the eluates. The content of Al³⁺ and Cu²⁺ as chemical impurities was also determined.