A novel technique for the separation of99mTc from99Mo

A new technique for the separation of^99mTc from low specific activity⁹⁹Mo is reported. A separation based on the principle of precipitation of⁹⁹Mo as calcium molybdate has been investigated. On precipitating⁹⁹MoO ₄ ^2– from alkaline solution as calcium molybdate under controlled conditions, the^99mTcO ₄ ^– is found to remain quantitatively in the supernatant solution with little carry-over of⁹⁹Mo. This calcium molybdate (⁹⁹Mo) could be redissolved and reprecipitated at regular intervals, yielding^99mTc quantitatively in aqueous neutral solutions. Calcium molybdate precipitates containing up to 1.5 GBq of⁹⁹Mo and 130–180 mg of molybdenum were prepared and evaluated. The performance in terms of repeated^99mTc separation gave yields of 75–93% with acceptable readionuclidic and radiochemical purity.     

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.     

A simple and sensitive separation technique of 99Mo and 99mTc from their equilibrium mixture

The present work describes a simple and inexpensive separation method of ⁹⁹Mo from the equilibrium mixture. The liquid–liquid extraction technique has been employed to separate ⁹⁹Mo and ^99mTc using triisooctylamine (TIOA). The ⁹⁹Mo and ^99mTc were quantitatively separated out in 2 M TIOA with tripled distilled water; ^99mTc was back extracted from TIOA organic phase to aqueous phase by 0.1 M DTPA. The species information or indirect speciation of molybdenum was also established by the extraction profile of the molybdenum.     

Desorption of99Mo from spent99Mo/99mTc generator

A simple method for desorption and purification of⁹⁹Mo from spent⁹⁹Mo/^99mTc generators is described. The alumina column was washed successively with 0.9% saline water, 35% H₂O₂, and then the⁹⁹Mo was eluted with 2M NH₄OH. Ammonia and residual H₂O₂ were removed by heating the eluate. Finally,⁹⁹Mo solution was passed through a 0.2 m membrane filter to remove precipitated aluminium hydroxide.     

Separation of99mTc from parent99Mo by solid-phase column extraction as a simple option for a new99mTc generator concept

Evidence is obtained to show that the liquidliquid extraction separation of^99mTc from⁹⁹Mo with methyl ethyl ketone, methyl propyl ketone and methyl isobutyl ketone can be transformed into a solid-phase column extraction procedure. The aqueous alkaline⁹⁹molybdate solution is immobilized on a column of a granular large-pore diatomaceous earch support, which is the neluted with the abovementioned extractants. Rapid and clean separation of^99mTc can be with all three solvents. The^99mTc can be back-extracted from the organic phase on a column filled with distilled water /or saline/ loaded granular diatomaceous earth /Extrelut^®/. The possibility of using the abovementioned procedure as a basis for a new^99mTc/⁹⁹Mo generator concept is envisaged.     

Separation and purification of 99mTc from 99Mo produced by electron linear accelerator

The medical radionuclide ⁹⁹Mo was produced by the ¹⁰⁰Mo(γ,n) reaction using bremsstrahlung photons generated by an electron linear accelerator. The amount of ⁹⁹Mo produced was compared to that predicted by calculation using the particles and heavy ion transport code system. From the ⁹⁹Mo produced, highly pure ^99mTc was separated using the so-called technetium master milker, and the chemical yield of ^99mTc was 83–99 %. The installation of a new complex using this method and the electron linear accelerator with the preferable specification was suggested, and a possibility to supply the demand of ^99mTc was discussed and shown.

     

Altered [99mTc]Tc-MDP biodistribution from neutron activation sourced 99Mo

Journal of Radioanalytical and Nuclear Chemistry - Given potential worldwide shortages of fission sourced 99Mo/99mTc medical isotopes there is increasing interest in alternate production...     

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.     

Radiochemical purity of99mTc radiopharmaceuticals

Some factors which could adversely affect the integrity of eight routine^99mTc radiopharmaceuticals have been investigated. The radiochemical purity of the preparations was determined both under standard (reconstitution according to the manufacturer's instructions) and under experimental conditions (higher contents of longlived⁹⁹Tc and copper). The influence of radiolytically produced hydrogen peroxide as well as the effect of introduction of air during the addition of pertechnetate as an example of poor labeling technique were examined. The radiochemical analyses were performed by paper and TL chromatography and electrophoresis.     

99mTc-centered one-pot synthesis for preparation of 99mTc radiotracers

Nuclear medicine relies on two main imaging modalities: single photon emission computed tomography (SPECT) and positron emission tomography (PET). Radiopharmaceuticals (or radiotracers) are the blood stream of nuclear medicine for the diagnosis or therapy of diseases. Diagnostic radiotracers that are small molecules labelled with a gamma-emitter for SPECT or positron-emitter for PET provide a non-invasive method to assess the disease or disease states and monitor the therapeutic efficacy of a specific treatment regime. Over the past four decades, radiopharmaceutical research has been practising one-pot synthesis at the tracer level (10(-7)-10(-6) M). Many (99m)Tc radiotracers currently used in nuclear medicine are routinely prepared by following the basic principles of one-pot synthesis. Unlike traditional organic one-pot synthesis, which often involves the formation of multiple C-C and C-heteroatom bonds in a single step, the (99m)Tc-centered one-pot synthesis requires the formation of multiple coordination bonds between Tc and various donor atoms, such as N, O, S and P. This review will illustrate how the (99m)Tc-centered one-pot synthesis is utilized for routine preparations of different (99m)Tc radiotracers.     

Highly Efficient Micro-Scale Liquid-Liquid In-Flow Extraction of 99mTc from Molybdenum

The trend to achieve even more compact-sized systems is leading to the development of micro-scale reactors (lab-on-chip) in the field of radiochemical separation and radiopharmaceutical production. Technetium-99m extraction from both high and low specific activity molybdenum could be simply performed by MEK-driven solvent extraction if it were not for unpractical automation. The aim of this work is to develop a solvent extraction and separation process of technetium from molybdenum in a micro-scale in-flow chemistry regime with the aid of a capillary loop and a membrane-based separator, respectively. The developed system is able to extract and separate quantitatively and selectively (91.0 ± 1.8% decay corrected) the [^99mTc]TcO₄Na in about 20 min, by using a ZAIPUT separator device. In conclusion, we demonstrated for the first time in our knowledge the high efficiency of a MEK-based solvent extraction process of ^99mTc from a molybdenum-based liquid phased in an in-flow micro-scale regime.     

99mTc放射性药物中的配位化学

在99mTc间接标记放射性药物中双功能螯合剂起到重要的连接作用,其在很大程度上决定了放射性药物的理化性质。99mTc标记放射性药物中常用的双功能螯合剂大都含有N、S、P等杂原子,本文以与锝核配位杂原子的不同对双功能螯合剂进行分类,分别对NxS(4-x)型配体、“3＋1”混合配体、含膦配体以及以[99mTc(CO)3]+为配位中心的99mTc放射性药物逐一进行介绍。     

Rapid estmation of technetium in99Mo−99mTc generators

A nomogram is presented to estimate the radiooctivity of^99mTc in⁹⁹Mo−^99mTc generators, based on equations of radioactive equilibrium. Since the parent element decays through two isomeric states of the daughter, the ratio of the total mass of technetium per millicurie of^99mTc is a function of the time elapsed between two consecutive elutions. Values of the amount of^99mTc expressed as a mole fraction or in moles or grams of total technetium per millicurie of^99mTc^m are also presented.     

Preparation of salicylidene-aminates labeled with99mTc

A series of bidentate and tetradentate ligands with azomethine and Ar–OH functional groups derived from salicylaldehyde and primary alkyl or aryl monoamines and diamines has been synthesized and labeled with^99mTc at various pH's using stannous chloride as reducing agent. The labeling efficiency was monitored by thin layer and paper chromatography.     

99mTc complexes of 1,3-propanedithiol derivatives

The labelling of 1,3-n alkylpropanedithiols and of 15-/1,3-dimercapto 2-propyl/ pentadecanoic acid by^99mTc has been performed by an exchange reaction with the hexachlorotechnetate ion^99mTcCl ₆ ^2– and by reduction of^99mTcO ₄ ^– with Sn/II/ in the presence of the ligand. The biological distribution of the exotechnetium complexes obtained by the latter method in mouse does not reveal a high tropism of these labelling compounds in relation to a particular tissue.     

Investigation of 99mTc labeled tumor seeking agents--usefulness of 99mTc-isoniazid

For the development of 99mTc labeled tumor seeking agents, 273 drugs and chemicals were evaluated. Agents labeled by SnCl2-HCl method were injected to rats bearing Yoshida sarcoma. Scintigrams of the rats 2 hours after injection and the excised tumor and organs placed on a plate were taken and evaluated their affinity to the tumor. Isoniazid (INH) was found to be the most useful agent as a result of this screening study. Intensive study on 99mTc-INH was subsequently performed. Another labeling method, FeSO4-H2SO4 method, was evaluated and shown to be superior in both absolute tumor uptake and tumor to muscle ratio. Uptake of 99mTc-INH to Yoshida sarcoma occurred early after injection and maintained its level until later time. On the other hand, radioactivity in the blood and muscle decreased rapidly; that is, tumor to blood and muscle ratio showed rapid increase. Other animal tumor models, mouse bearing Ehrlich tumor or Sarcoma 180, were also used to evaluate the usefulness of 99mTc-INH. The labeled agent showed good localization in these tumors too. In conclusion 99mTc-INH might be a good tumor seeking agent and further clinical trials would be warrant.