Preparation of 95mTc radiotracer

Fikrle, Marek; Kučera, Jan; Šebesta, F.

doi:10.1007/s10967-010-0737-8

Cited by 4 publications

(2 citation statements)

References 12 publications

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“…The 177m Lu- 177 Lu separation has been performed using liquid-liquid extraction (LLE). LLE has been explored several times before in the development of other radionuclide generators, such as 99 Mo/ 99m Tc, 68 Ge/ 68 Ga, 188 Re/ 188 W, and 90 Y/ 90 Sr radionuclide generators (Le Minh & Lengyel, 1989; Fikrle et al, 2010; Bhatia & Turel, 1989; Boyd, 1982; Ehrhardt & Welch, 1978; Mushtaq et al, 2007; Dutta & Mohapatra, 2013). The present work demonstrates the application of LLE in 177 Lu- 177m Lu separation which can potentially lead to a commercial 177m Lu/ 177 Lu radionuclide generator.…”

Section: Introductionmentioning

confidence: 99%

Radionuclide generator-based production of therapeutic 177Lu from its long-lived isomer 177mLu

Bhardwaj

Wolterbeek

Denkova

et al. 2019

EJNMMI radiopharm. chem.

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Background In this work, a lutetium-177 ( 177 Lu) production method based on the separation of nuclear isomers, 177m Lu & 177 Lu, is reported. The 177m Lu- 177 Lu separation is performed by combining the use of DOTA & DOTA-labelled peptide (DOTATATE) and liquid-liquid extraction. Methods The 177m Lu cations were complexed with DOTA & DOTATATE and kept at 77 K for periods of time to allow 177 Lu production. The freed 177 Lu ions produced via internal conversion of 177m Lu were then extracted in dihexyl ether using 0.01 M di-(2-ethylhexyl) phosphoric acid (DEHPA) at room temperature. The liquid-liquid extractions were performed periodically for a period up to 35 days. Results A maximum 177 Lu/ 177m Lu activity ratio of 3500 ± 500 was achieved with [ 177m Lu]Lu-DOTA complex, in comparison to 177 Lu/ 177m Lu activity ratios of 1086 ± 40 realized using [ 177m Lu]Lu-DOTATATE complex. The 177 Lu- 177m Lu separation was found to be affected by the molar ratio of lutetium and DOTA. A 177 Lu/ 177m Lu activity ratio up to 3500 ± 500 was achieved with excess DOTA in comparison to 177 Lu/ 177m Lu activity ratio 1500 ± 600 obtained when lutetium and DOTA were present in molar ratio of 1:1. Further, the 177 Lu ion extraction efficiency, decreases from 95 ± 4% to 58 ± 2% in the presence of excess DOTA. Conclusion The reported method resulted in a 177 Lu/ 177m Lu activity ratio up to 3500 after the separation. This ratio is close to the lower end of 177 Lu/ 177m Lu activity ratios, attained currently during the direct route 177 Lu production for clinical applications (i.e. 4000–10,000). This study forms the basis for further extending the liquid-liquid extraction based 177m Lu- 177 Lu separation in order to lead to a commercial 177m Lu/ 177 Lu radionuclide generator. Electronic supplementary material The online version of this article (10.1186/s41181-019-0064-5) contains supplementary material, which is available to authorized users.

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Section: Introductionmentioning

confidence: 99%

Radionuclide generator-based production of therapeutic 177Lu from its long-lived isomer 177mLu

Bhardwaj

Wolterbeek

Denkova

et al. 2019

EJNMMI radiopharm. chem.

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“…Some of them, such as TEVA Spec resin (Aliquat-336 or tricapryl methyl ammonium chloride extractant impregnated in an inert substrate) and activated charcoal, adsorb TcO 4 − ions strongly in dilute nitric acid solutions. However, the strong acidic solution (8 M HNO 3 ) required for recovery of TcO 4− ions is not preferred for practical application on the basis of daily use in nuclear medicine[119][120][121][122][123]. Some sorbents, such as ABEC (aqueous biphasic extraction chromatographic) resin and strong anion-exchange (Dowex-1×8) resin, adsorb TcO 4 −…”

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confidence: 99%

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness of
Le¹
2014
Science and Technology of Nuclear Installations
16
0
8
0
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A review on theMosources available today and on theTcgenerators developed up to date for increasing the effectiveness ofMoutilisation is performed in the format of detailed description of the features and technical performance of the technological groups of theMoproduction andTcrecovery. The latest results of the endeavour in this field are also surveyed in regard of the technical solution for overcoming the shortage ofMosupply. The technological topics are grouped and discussed in a way to reflect the similarity in the technological process of each group. The following groups are included in this review which are high specific activityMo: the current issues of production, the efforts of more effective utilisation, and the high specific activityMo-basedTcgenerator andTcconcentration units; low specific activityMo: theMoproduction based on neutron capture and accelerators and the direct production ofTcand the methods of increasing the specific activity ofMousing Szilard-Chalmers reaction and high electric power isotopic separator; up-to-date technologies ofTcrecovery from low specific activityMo: the solvent extraction-basedTcgenerator, the sublimation methods forMo/Tcseparation, the electrochemical method forTcrecovery, and the column chromatographic methods forTcrecovery. Besides the traditionalTc-generator systems, the integratedTcgenerator systems (Tcgenerator column combined with postelution purification/concentration unit) are discussed with the format of process diagram and picture of real generator systems. These systems are the technetium selective sorbent column-based generators, the high Mo-loading capacity column-based integratedTcgenerator systems which include the saline-eluted generator systems, and the nonsaline aqueous and organic solvent eluent-eluted generator systems using high Mo-loading capacity molybdategel and recently developed sorbent columns.Tcconcentration methods used in theTcrecovery from low specific activityMoare also discussed with detailed process diagrams which are surveyed in two groups forTcconcentration from the saline and nonsalineTc-eluates. The evaluation methods for the performance ofTc-recovery/concentration process and for theTc-elution capability versus Mo-loading capacity of generator column produced using low specific activityMosource are briefly reported. Together with the theoretical aspects ofTc/Moand sorbent chemistry, these evaluation/assessment processes will be useful for any further development in the field of theTcrecovery andMo/Tcgenerator production.

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Simple separation of technetium from molybdenum for tracer isotope production

Kmak,

Despotopulos,

Kerlin

2024

J Radioanal Nucl Chem

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Preparation of 95mTc radiotracer

Cited by 4 publications

References 12 publications

Radionuclide generator-based production of therapeutic 177Lu from its long-lived isomer 177mLu

Radionuclide generator-based production of therapeutic 177Lu from its long-lived isomer 177mLu

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness of
Le¹
2014
Science and Technology of Nuclear Installations
16
0
8
0
View full text Add to dashboard Cite

Simple separation of technetium from molybdenum for tracer isotope production

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Preparation of 95mTc radiotracer

Cited by 4 publications

References 12 publications

Radionuclide generator-based production of therapeutic 177Lu from its long-lived isomer 177mLu

Radionuclide generator-based production of therapeutic 177Lu from its long-lived isomer 177mLu

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness ofLe1 2014Science and Technology of Nuclear Installations16080View full textAdd to dashboardCite

Simple separation of technetium from molybdenum for tracer isotope production

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About

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness of
Le¹
2014
Science and Technology of Nuclear Installations
16
0
8
0
View full text Add to dashboard Cite