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155Tb production by cyclotrons: what level of 155Gd enrichment allows clinical applications?
Barbaro, Francesca; Canton, Luciano; Uzunov, Nikolay; De Nardo, Laura; Melendez-Alafort, Laura.
Afiliación
  • Barbaro F; INFN-Padua, National Institute of Nuclear Physics, Via Marzolo 8, 35131, Padua, Italy.
  • Canton L; Department of Physics and Astronomy, University of Padua, Via Marzolo 8, 35131, Padua, Italy.
  • Uzunov N; INFN-Padua, National Institute of Nuclear Physics, Via Marzolo 8, 35131, Padua, Italy.
  • De Nardo L; INFN-Legnaro National Laboratories, National Institute of Nuclear Physics, Viale Dell'Università 2, 35020, Legnaro, Italy.
  • Melendez-Alafort L; INFN-Padua, National Institute of Nuclear Physics, Via Marzolo 8, 35131, Padua, Italy. laura.denardo@unipd.it.
EJNMMI Phys ; 11(1): 26, 2024 Mar 15.
Article en En | MEDLINE | ID: mdl-38485872
ABSTRACT

BACKGROUND:

155Tb represents a potentially useful radionuclide for diagnostic medical applications, but its production remains a challenging problem, in spite of the fact that many production routes have been already investigated and tested. A recent experimental campaign, conducted with low-energy proton beams impinging on a 155Gd target with 91.9% enrichment, demonstrated a significant co-production of 156gTb, a contaminant of great concern since its half-life is comparable to that of 155Tb and its high-energy γ emissions severely impact on the dose released and on the quality of the SPECT images. In the present investigation, the isotopic purity of the enriched 155Gd target necessary to minimize the co-production of contaminant radioisotopes, in particular 156gTb, was explored using various computational simulations.

RESULTS:

Starting from the recent experimental data obtained with a 91.9% 155Gd-enriched target, the co-production of other Tb radioisotopes besides 155Tb has been theoretically evaluated using the Talys code. It was found that 156Gd, with an isotopic content of 5.87%, was the principal contributor to the co-production of 156gTb. The analysis also demonstrated that the maximum amount of 156Gd admissible for 155Tb production with a radionuclidic purity higher than 99% was 1%. A less stringent condition was obtained through computational dosimetry analysis, suggesting that a 2% content of 156Gd in the target can be tolerated to limit the dose increase to the patient below the 10% limit. Moreover, it has been demonstrated that the imaging properties of the produced 155Tb are not severely affected by this level of impurity in the target.

CONCLUSIONS:

155Tb can be produced with a quality suitable for medical applications using low-energy proton beams and 155Gd-enriched targets, if the 156Gd impurity content does not exceed 2%. Under these conditions, the dose increase due to the presence of contaminant radioisotopes remains below the 10% limit and good quality images, comparable to those of 111In, are guaranteed.
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Texto completo: 1 Colección: 01-internacional Base de datos: MEDLINE Idioma: En Revista: EJNMMI Phys Año: 2024 Tipo del documento: Article País de afiliación: Italia Pais de publicación: Alemania

Texto completo: 1 Colección: 01-internacional Base de datos: MEDLINE Idioma: En Revista: EJNMMI Phys Año: 2024 Tipo del documento: Article País de afiliación: Italia Pais de publicación: Alemania