General principles of enzymatic methods and their use in the determination of the radiochemical purity of mono-and disaccharides labelled with14C

General principles of enzymatic methods for the determination of radiochemical purity of natural¹⁴C-mono-and-disaccharides are suggested, and analytical schemes using these principles have been worked out. The enzymatic method of determining the radiochemical purity of¹⁴C-glucose is given as an illustration.     

Synthesis of N-isopropyl-p-123I-amphetamine and biodistribution in rats

The described labelling and purification preparation of N-isopropyl-p-¹³¹I-amphetamine /¹³¹I-IMP/ represents a fast and efficient method to obtain a compound that fulfils all criteria of purity for its in-vivo application. After isotope exchange and quality control¹³¹I-IMP could be obtained with radiochemical yields in the range between 68% and 78% with a radiochemical purity of 98–99%. As demonstrated in animal experiments the cerebral affinity of IMP offers a possibility for the diagnosis of brain diseases in clinical studies when the product is labelled with¹²³I.     

An improved method for the preparation of [<Superscript>14</Superscript>C]thiourea of high radiochemical purity

Summary An improved method for the preparation of [¹⁴C]thiourea of high radiochemical purity is described. [¹⁴C]thiourea is prepared by the barium cyanamide route and is purified by vacuum-sublimation. The labeled product showed ammonium [¹⁴C]thiocyanate as a radiochemical impurity in the range of 2-4%. This was further purified by silica-gel column chromatography to get the product having more than 99% radiochemical purity.     

Kit preparation of153Sm-EDTMP and factors affecting radiochemical purity and stability

A fast kit method was developed for the production of¹⁵³Sm-EDTMP in two steps avoiding the use of nitric acid, evaporation and sterilization of the final solution by autoclave. Methods of analysis for the determination of chemical and radiochemical purity in the radiopharmaceutical solution were established. Factors affecting radiochemical purity and stability of the complex as the molar ratio of EDTMP/Sm, concentration of phosphate buffer and neutralization of EDTMP prior kit preparation were also analyzed. The use of this radiopharmaceutical in rabbits and patients showed selective skeletal uptake.     

Labeling of atenolol with radioactive iodine-125 using <Emphasis Type="Italic">N</Emphasis>-bromosuccinimide and hydrogen peroxide as oxidizing agents

An adopted method for the preparation of high radiochemical purity ¹²⁵I-atenolol was investigated. Direct radioiodination of atenolol was carried out using N-bromosuccinamide or hydrogen peroxide as an oxidizing agent. The reaction proceeds well within 30 min at room temperature (25 ± 1 °C) and afforded a radiochemical yield up to 97% as pure as ¹²⁵I-atenolol. Different chromatographic techniques (electrophoresis, TLC and HPLC) were used to determine the radiochemical yield and purity of the labeled product. Biodistribution studies were carried out in normal Albino Swiss mice and the results indicate that ¹²⁵I-atenolol can be used safely as myocardial imaging agent.     

A modified method for no carrier added radioiodination of L-tyrosine via chloramine-T as an oxidizing agent

A modified method for the preparation of L-[^131/123I] iodotyrosine as a brain imaging agent is described. The method is based on direct electrophilic radioiodination of L-tyrosine with NaI [^131/123I] using chloramine-T (CAT) and 0.001 g KI as a carrier at pH 7.0. The product was purified by reverse phase high performance liquid chromatography (HPLC). A high radiochemical yield up to 85% of L-[^131/123I] iodotyrosine has been achieved with radiochemical purity of greater than 97%. The relation between the pKa of L-tyrosine and pH of the reaction medium was calculated in order to correlate the radiochemical yield of L-[^131/123I] iodotyrosine and the state of the three ionizable groups of L-tyrosine. Also, the influence of the reaction conditions on the radiochemical yield of L-[^131/123I] iodotyrosine was investigated.     

新型除草剂丙酯草醚A环14C均标记合成和鉴定

以U-¹⁴C-对氨基苯甲酸为前体, 通过酯化、缩合、还原和取代四步反应获得了A环¹⁴C均标记的丙酯草醚, 用PHPLC对其进行纯化. 采用HPLC-MS(ESI), MS(EI)和¹H NMR验证了其结构, 通过HPLC(外标法)确定其化学纯度大于98%; HPLC-LSC和TLC-IIA两种方法分析表明, 其放射化学纯度大于98%, 其比活度为1.089±0.011 mCi/mmol. 合成的化学收率和放化收率均为53%.     

Radioiodination of N-[3-(4-morphilino)propyl]-N-methyl-2-hydroxy-5-iodo-3-methyl-benzylamine (ERC9) via isotopic exchange reaction

Summary A simple method for labeling ERC9 with radioactive iodine has been carried out via nucleophilic substitution radioiodination. The factors affecting the radiochemical yield of the labeling of ERC9, such as pH of the medium, substrate concentration and temperature were investigated. Chromatographic analysis technique was used to determine the radiochemical yield and purity. Kinetics and thermodynamic parameters indicated a second order reaction. Activation energy for the isotopic exchange reaction between ERC9 and ¹²⁵I^- was calculated to be 24.4 kJ/mol.     

Labeling of ursodeoxycholic acid with technetium-99m for hepatobiliary imaging

An adopted method for the preparation of high radiochemical purity ^99mTc-ursodeoxycholic acid (UDCA) was conducted with a high radiochemical yield up to 97.5 %. The reaction proceeds well using 2 mg UDCA, 50 μg tin chloride in solution of pH 8 at room temperature for 30 min. The radiochemical yield was up to 97.5 % as pure as ^99mTc-UDCA. Different chromatographic techniques (paper chromatography and electrophoresis) were used to evaluate the radiochemical yield and purity of the labeled product. Biodistribution studies were carried out in Albino Swiss mice at different time intervals after administration of ^99mTc-UDCA. The uptake of ^99mTc-UDCA in the liver gave the chance to diagnose it. The results indicate that the labeled compound cleared from the systematic circulation within 2 h after administration and majority of organs showed significant decrease in uptake of ^99mTc-UDCA. Finally, the liver uptake was high and the results indicate the possibility of using ^99mTc-UDCA for hepatobiliary imaging.     

Determination of iodine in biological materials by neutron activation analysis

A method of determination of iodine (total and PBI) in serum, urine and other biological materials has been developed. The method consists in a gamma-spectrometric measurement of¹²⁸I activity after its radiochemical separation. The radiochemical separation procedure includes wet decomposition of the samples in a nitric acid medium followed by a few separation steps, the essential step being the substoichiometric extraction of iodide with a chloroform solution of tetraphenylarsonium chloride. Owing to the application of the substoichiometric separation, a high radiochemical purity of the separated iodine is achieved and the determination of the yield of radiochemical separation is not necessary.     

A rapid and high-yield aqueous phase preparation procedure for123I-labelled meta-iodobenzylguanidine

A new, aqueous phase preparation procedure for¹²³I-mIBG /meta-iodobenzylguanidine/ is described. It comprises a copper-catalyzed exchange reaction between aqueous¹²³I-iodide and mIBG at 150 °C for 45 min, a purification via anion-exchange chromatography, and a sterilization via micropore filtration. Overall preparative yield, radiochemical purity and specific activity amount to >90%, >99.7% and >10¹⁵ Bq.mol^–1 mIBG, respectively. Other features are simplicity /no evaporation of water or other solvents/, reproducibility of labelling yield and radiochemical purity, and speed /total time required 1.5 h/.     

Stability of L-[S-methyl-11C]methionine solutions

For clinical PET studies L-[S-methyl-¹¹C]methionine ([¹¹C]MET) solutions have been prepared in both high doses and specific activities (up to 48.1 GBq and 370 GBq/mmol, respectively) with high radiochemical purity (>99%). The stability of these preparations was investigated by HPLC to ensure the radiopharmaceutical efficacy during the usable shelf life. Under our routine conditions the observed radiochemical purity loss never exceeded 3.5% one hour after EOS. The decomposition rate was affected by total activity and chemical composition of the solutions.     

A facile preparation of ammonium [<Superscript>14</Superscript>C]thiocyanate

Summary An attractive and simple method has been developed for the preparation of ammonium [¹⁴C]thiocyanate from [¹⁴C]thiourea which eliminates the necessity of handling highly hazardous potassium [¹⁴C] cyanide. [¹⁴C]thiourea was isomerized to ammonium [¹⁴C]thiocyanate by heating the aqueous solution of thiourea (12%) in a sealed tube at 160 °C for 24 hours. The product formed was purified by silica-gel column chromatography. A radiochemical yield of 92.7% was obtained based on [¹⁴C]thiourea. The specific activity of the product obtained was 53.3 mCi/mmol (1.97 GBq/mmol) and the radiochemical purity was greater than 99%. This method has not been reported so far for the production of this labeled compound.     

Purity control of the radiopharmaceutical thiamine pyrophosphate-Sn-99mTc

A new purity control method was developed in order to assure the radiochemical purity of thiamine pyrophosphate-Sn-^99mTc. The method described consists in ascending cromatography using Whatman N^o 1 for support and 5% sodium citrate as solvent. It is capable of detecting free^99mTcO ₄ ^– and colloid formation, the most frequent impurities found in^99mTc radiopharmaceuticals.     

A simple and quick method for the preparation of radionuclide <Superscript>87</Superscript>Y/<Superscript>87m</Superscript>Sr generator using the <Superscript>nat</Superscript>Rb(α,xn)<Superscript>87</Superscript>Y reaction

A rapid method for the preparation of ⁸⁷Y/^87mSr radionuclide generator from a rubidium chloride target irradiated with 35 MeV α-particles is described. A simple two-step procedure is used to obtain a carrier-free ^87mSr isotope with a high enough radiochemical yield and high purity in the final aqueous fraction.     

Optimization of the preparation conditions of radioiodoepidepride: A dopamine D<Subscript>2</Subscript>receptor antagonist radioligand

Summary [¹²⁵I]iodepidepride, (s)-(-)-[(1-ethyl-2-pyrrolidinyl)methyl]-5-[¹²⁵I]-iodo-2,3-dimethoxybenzamide is the iodine substituted analogue of isoremoxipride, both of which are very potent dopamine D₂-antagonists. Epidepride was radioiodinated using different oxidizing agents such as chloramine-T, iodogen, iodogen glass frit and hydrogen peroxide. Chloramine-T is a powerful oxidizing agent compared to both iodogen and hydrogen peroxide so that the side products, especially the chlorinated epidepride, decreases the radiochemical yield. This chlorinated epidepride is minimized in the case of iodogen and iodogen glass frit and are not observed in case of the non-chlorinated oxidizing agent hydrogen peroxide. TLC and HPLC were used to analyze the reaction components and to estimate both the radiochemical yield and purity. The reaction parameters such as reaction time, pH, epidepride and oxidizing agent concentrations and the stabilty of the final product were studied to optimize the radiochemical yield and purity. The optimized radiochemical yield was about 90% and the radiochemical purity of the final product was 99.9%.     

Radiolabeling of EGCG with 125I and its biodistribution in mice

The aim of the present study was to label EGCG with ¹²⁵I and to determine its radiopharmaceutical potential in mice. EGCG was labeled with ¹²⁵I using the iodogen method. The labeling yield and the radiochemical purity of ¹²⁵I–EGCG were determined by radio thin-layer chromatography (RTLC). The Labeling yield was approximately 89.4 %. The radiochemical purity was approximately 96.4 %. The biodistribution studies of the labeled compound (specific activity; 0.47 TBq/μg) were performed in male Kunming mice. The uptakes of ¹²⁵I–EGCG in some organs were determined at different time after injection to the mice. The radioactivity in each organ was counted and the percentage of injected activity per gram of tissue weight (%ID/g) for each organ and blood was calculated. Incorporation of radioactivity in the various tissue/organ was confirmed by microautoradiography. ¹²⁵I–EGCG uptake in the stomach and salivary gland was higher than other organ/tissue. The black silver grains was concentrated in the nucleus, cytoplasm, intercellular substance and capillaries of that various organs, and its unevenly distributed. Thus, ¹²⁵I–EGCG may be radiopharmaceutical for the imaging of the stomach and salivary gland.     

Extraction chromatographic separation of carrier-free90Y from90Sr/90Y generator by crown ether coated silica gels

A remarkable extraction chromatographic method for the preparation of⁹⁰Y of high radiochemical purity has been developed. The generator consists of silica gel coated crown ether. It functions as a strong adsorber for⁹⁰Sr and in the meantime high purity of⁹⁰Y is eluted with a dilute solution of picric acid after a suitable period. The experiments indicated that DC18C6 coated silica gel is better than that of DB18C6 coated. The extraction capacity of strontium on 3.8% DC18C6 coated silica gel is 5.6 mg Sr/g silica gel. Yttrium is obtained with more than 95% milking yield with radionuclide purity greater than 99.9%. The extraction chromatographic generator does not change its characteristics even after 5 elutions.     

11C-clomipramine: Synthesis and analysis

A method is described for the labelling of the antidepressant clomipramine with¹¹C. A product of 10–20 mCi is obtained in 40 min after the irradiation. The chemical and radiochemical purity of¹¹C-clomipramine is investigated.     

Determination of radiochemical purity of chlormerodrin-203 by electrophoretic method

An electrophoretic method to control the radiochemical purity of chlormerodrin-203 is described. Optimum conditions for the separation of inorganic and organically bound mercury-203 were determined by investigating its mobility in the concentration range of 1·10⁻⁵–1·10⁻² M NaCl. Maximum separation, of²⁰³Hg and hydroxychlormerodrin was achieved at 0.05M NaCl, at the potential gradient of 8V/cm for 2 hrs.