Analytical and radioanalytical quality control of purity and stability of radiopharmaceutical compound [186gRe]Re-HEDP for bone metastases pain palliation

Summary The nuclear properties of ^186gRe make it a useful agent for radionuclide therapy and imaging. The coordination compound [^186gRe]Re-HEDP has proved to be a successful bone seeking agent for palliation of metastatic bone pain. Chemical, radiochemical and radionuclidic purity of commercial radiopharmaceutical [^186gRe]Re-HEDP have been checked by means by γ- and β-spectrometries, INAA and paper radio-chromatography. The results indicate a good radionuclidic purity, with levels of contamination from the short-lived ¹⁸⁸Re well below the required specifications. After injection of the radiopharmaceutical, the radiochemical measurements conducted in vivo, on biological matrices, blood, plasma and urine, have shown that, entering the systemic circulation, ^186gRe dissociates from the bis-phosphonate complex as hydrosoluble [^186gRe]ReO₄-, and the two chemical species follow different biokinetics.     

Paper radiochromatography for evaluation of radiochemical purity and stability of [<Superscript>186g</Superscript>Re]Re-HEDP in biological samples after human administration

[^186gRe]Re-HEDP is a radiopharmaceutical used for pain palliation in bone metastases from various primary tumors. The negatron emitter with 〈E _β 〉 = 357 keV ^186gRe is suitable to irradiate cancer and inflammatory cells, but it needs labeling bis-phosphonates as vectors to reach target tissue. Paper radiochromatography was used to evaluate the radiochemical purity of [^186gRe]Re-HEDP in radiopharmaceutical solution as well as in biological samples (serum and urine) from treated patients, in order to follow bone-targeting and excretion. Following the activity concentration in each sample vs. time it is effective to elaborate a bio-kinetic model of the radiopharmaceutical and to optimize administration protocols.     

Purification and separation of <Superscript>239+240</Superscript>Pu and <Superscript>241</Superscript>Am in biological samples by anion-exchange and extraction chromatography for high resolution alpha-spectrometry analyses

Many biological samples (urines and faeces) have been analyzed by means of chromatographic extraction columns, utilizing two different resins (AG 1-X2 resin chloride and TRU), in order to detect the possible internal contamination of ^239+240Pu and ²⁴¹Am for some workers of a reprocessing nuclear plant in the decommissioning phase. The results obtained show on one hand the great suitability of the first resin for the determination of plutonium, and on the other, the great selectivity of the second one for the determination of americium.     

Radioanalytical determination of 239+240Pu and 241Am in bioassay samples by anion exchange and extraction chromatography: Preliminary considerations about the two methods

During the radiation protection surveillance of exposed workers samples of urine and faeces were collected. Anion exchange chromatography was used for the separation of Pu. We investigated a technique to purify and separate Pu and Am isotopes using extraction chromatography with TRU resin. We tested different procedures to dissolve organic matter and eliminate interferences for chromatographic elution. At the end of the proces we have succeeded in electroplating the two radionuclides separately. We have also studied extraction chromatography with UTEVA resin to purify Pu isotopes and separate it from natural uranium radioisotopes, present in some biological samples. We validated a method for the determination of Pu in biological samples and a rather constant chemical yield and resolved peaks were obtained. The preliminary studies on TRU resin have indicated that it is possible to combine extraction and anion-exchange chromatography for analysing separately Pu and Am isotopes from the same sample aliquote.     

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.     

Determination of 90Sr in urine samples and 89Sr/90Sr in water samples by chemical separation and Cherenkov counting with LSC system

Journal of Radioanalytical and Nuclear Chemistry - In order to determine radiostrontium with a satisfactory chemical yield, calculated by an external standard, and a low level of MDC a...