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A solvent-extraction module for cyclotron production of high-purity technetium-99m.
Martini, Petra; Boschi, Alessandra; Cicoria, Gianfranco; Uccelli, Licia; Pasquali, Micòl; Duatti, Adriano; Pupillo, Gaia; Marengo, Mario; Loriggiola, Massimo; Esposito, Juan.
Afiliação
  • Martini P; Laboratory of Nuclear Medicine, Department of Morphology, Surgery and Experimental Medicine, University of Ferrara, Italy; Legnaro National Laboratories, Italian National Institute for Nuclear Physics (LNL-INFN), Italy. Electronic address: petra.martini@unife.it.
  • Boschi A; Laboratory of Nuclear Medicine, Department of Morphology, Surgery and Experimental Medicine, University of Ferrara, Italy. Electronic address: alessandra.boschi@unife.it.
  • Cicoria G; Department of Nuclear Medicine, St. Orsola Hospital, Italy.
  • Uccelli L; Laboratory of Nuclear Medicine, Department of Morphology, Surgery and Experimental Medicine, University of Ferrara, Italy.
  • Pasquali M; Laboratory of Nuclear Medicine, Department of Morphology, Surgery and Experimental Medicine, University of Ferrara, Italy.
  • Duatti A; Legnaro National Laboratories, Italian National Institute for Nuclear Physics (LNL-INFN), Italy; Department of Chemical and Pharmaceutical Sciences, University of Ferrara, Italy.
  • Pupillo G; Legnaro National Laboratories, Italian National Institute for Nuclear Physics (LNL-INFN), Italy.
  • Marengo M; Department of Nuclear Medicine, St. Orsola Hospital, Italy.
  • Loriggiola M; Legnaro National Laboratories, Italian National Institute for Nuclear Physics (LNL-INFN), Italy.
  • Esposito J; Legnaro National Laboratories, Italian National Institute for Nuclear Physics (LNL-INFN), Italy.
Appl Radiat Isot ; 118: 302-307, 2016 Dec.
Article em En | MEDLINE | ID: mdl-27744212
ABSTRACT
The design and fabrication of a fully-automated, remotely controlled module for the extraction and purification of technetium-99m (Tc-99m), produced by proton bombardment of enriched Mo-100 molybdenum metallic targets in a low-energy medical cyclotron, is here described. After dissolution of the irradiated solid target in hydrogen peroxide, Tc-99m was obtained under the chemical form of 99mTcO4-, in high radionuclidic and radiochemical purity, by solvent extraction with methyl ethyl ketone (MEK). The extraction process was accomplished inside a glass column-shaped vial especially designed to allow for an easy automation of the whole procedure. Recovery yields were always >90% of the loaded activity. The final pertechnetate saline solution Na99mTcO4, purified using the automated module here described, is within the Pharmacopoeia quality control parameters and is therefore a valid alternative to generator-produced 99mTc. The resulting automated module is cost-effective and easily replicable for in-house production of high-purity Tc-99m by cyclotrons.
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Texto completo: 1 Coleções: 01-internacional Base de dados: MEDLINE Idioma: En Revista: Appl Radiat Isot Assunto da revista: MEDICINA NUCLEAR / SAUDE AMBIENTAL Ano de publicação: 2016 Tipo de documento: Article

Texto completo: 1 Coleções: 01-internacional Base de dados: MEDLINE Idioma: En Revista: Appl Radiat Isot Assunto da revista: MEDICINA NUCLEAR / SAUDE AMBIENTAL Ano de publicação: 2016 Tipo de documento: Article