Radionuclide Generators

Rösch, Frank; Knapp, F. F.

doi:10.1007/978-1-4419-0720-2_40

Cited by 19 publications

(26 citation statements)

References 234 publications

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“…This has been accomplished with the aid of positron emission tomography (PET), which involves the same vector biomolecules labelled with positron emitters, and was first demonstrated with 68 Ga-labelled somatostatin (SST) analogues for diagnostic imaging of neuroendocrine tumours [1]. Since then growing interest in other positron emitters obtained in generator systems has been observed [2,3]. The increasing availability of new radionuclides with diagnostic and therapeutic properties offers new possibilities for individualized nuclear medicine options.…”

Section: Introductionmentioning

confidence: 99%

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Comparison of receptor affinity of natSc-DOTA-TATE versus natGa-DOTA-TATE

Koumarianou¹,

Pawlak²,

Korsak³

et al. 2011

Nucl Med Rev Cent East Eur.

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Section: Introductionmentioning

confidence: 99%

“…The use of 44 Sc with a half-life more than 3 times longer than that of 68 Ga (T ½ = 67.71 min) makes it an useful alternative for diagnostic purposes but also for dosimetry and 47 Sc as radiotherapeutic agents [5]. The availability of 44 Sc is also increasing [3,6].…”

Section: Introductionmentioning

confidence: 99%

Comparison of receptor affinity of natSc-DOTA-TATE versus natGa-DOTA-TATE

Koumarianou¹,

Pawlak²,

Korsak³

et al. 2011

Nucl Med Rev Cent East Eur.

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“…Furthermore, some gel and distillation generators have been developed [cf . 8,9] but their overall efficiencies are not comparable to that of the alumina column generator. In view of the situation, combined with the fact that for production purposes irradiations are mostly done at medium-flux reactors, the method of choice for production of 99 Mo for medical use is the fission process.…”

Section: Gamma Emitters For Spectmentioning

confidence: 92%

The present and future of medical radionuclide production

Qaim

2012

Radiochimica Acta

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Reactor and cyclotron production of medical radionuclides / γ -ray emitters for SPECT / Positron emitters for PET / Corpuscular radiation emitters for internal radiotherapy / Low and intermediate energy nuclear reactions / Radionuclide generators / Future directionsSummary. Medical radionuclide production technology is well established. Both reactors and cyclotrons are utilized for production; the positron emitters, however, are produced exclusively using cyclotrons. A brief survey of the production methods of most commonly used diagnostic and therapeutic radionuclides is given. The emerging radionuclides are considered in more detail. They comprise novel positron emitters and therapeutic radionuclides emitting low-range electrons and α-particles. The possible alternative production routes of a few established radionuclides, like 68 Ga and 99m Tc, are discussed. The status of standardisation of production data of the commonly used as well as of some emerging radionuclides is briefly mentioned. Some notions on anticipated future trends in the production and application of radionuclides are considered.

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“…Some other generator systems have also been proposed (for a review of production routes cf . [131,132]). A few interesting systems for furnishing some novel positron emitters are listed in Table 3.…”

Section: Production Of Novel Parent Generator Radionuclidesmentioning

confidence: 97%

Development of novel positron emitters for medical applications: nuclear and radiochemical aspects

Qaim¹

2011

Ract

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In molecular imaging, the importance of novel longer lived positron emitters, also termed as non-standard or innovative PET radionuclides, has been constantly increasing, especially because they allow studies on slow metabolic processes and in some cases furnish the possibility of quantification of radiation dose in internal radiotherapy. Considerable efforts have been invested worldwide and about 25 positron emitters have been developed. Those efforts relate to interdisciplinary studies dealing with basic nuclear data, high current charged particle irradiation, efficient radiochemical separation and quality control of the desired radionuclide, and recovery of the enriched target material for reuse. In this review all those aspects are briefly discussed, with particular reference to three radionuclides, namely 64 Cu, 124 I and 86 Y, which are presently in great demand. For each radionuclide several nuclear routes were investigated but the ( p, n) reaction on an enriched target isotope was found to be the best for use at a small-sized cyclotron. Some other positron emitting radionuclides, such as 55 Co, 76 Br, 89 Zr, 82m Rb, 94m Tc, 120 I, etc., were also produced via the low-energy ( p, n), ( p, α) or (d, n) reaction. On the other hand, the production of radionuclides 52 Fe, 73 Se, 83 Sr, etc. using intermediate energy ( p, xn) or (d, xn) reactions needs special consideration, the nuclear data and chemical processing methods being of key importance. In a few special cases, a high intensity 3 He-or α-particle beam could be an added advantage. The production of some potentially interesting positron emitters via generator systems, for example 44 Ti/ 44 Sc, 72 Se/ 72 As and 140 Nd/ 140 Pr is considered. The significance of new generation high power accelerators is briefly discussed.

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Radionuclide Generators

Cited by 19 publications

References 234 publications

Comparison of receptor affinity of natSc-DOTA-TATE versus natGa-DOTA-TATE

Comparison of receptor affinity of natSc-DOTA-TATE versus natGa-DOTA-TATE

The present and future of medical radionuclide production

Development of novel positron emitters for medical applications: nuclear and radiochemical aspects

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