Utilization of (p, 4n) reaction for 86Zr production with medium energy protons and development of a 86Zr → 86Y radionuclide generator

Baimukhanova, A.; Radchenko, Valery; Kozempel, Ján; Marinova, A.; Brown, Victoria; Карандашев, В. К.; Karaivanov, Dimitar Petkov; Schaffer, Paul; Filosofov, D.V.

doi:10.1007/s10967-018-5730-7

Cited by 10 publications

(2 citation statements)

References 22 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Many cyclotron-based routes to 86 Y production have been demonstrated, including 86 Sr(p,n) 86 Y, 88 Sr(p,3n) 86 Y, 90 Zr(p,2p3n) 86 Y, nat Rb( 3 He,xn) 86 Y, and, most recently, indirectly via 89 Y(p,4n) 86 Zr → 86 Y. − Currently the most practical production route is 86 Sr(p,n) 86 Y, as low-energy protons (7–14 MeV) can be used to achieve good yields. The drawback of this strategy is the need for enriched 86 Sr to minimize the coproduction of radioisotopic impurities ( 87/88 Y), which necessitates diligent recycling of the target material .…”

Section: Yttriummentioning

confidence: 99%

Radioactive Main Group and Rare Earth Metals for Imaging and Therapy

2018

View full text Add to dashboard Cite

Radiometals possess an exceptional breadth of decay properties and have been applied to medicine with great success for several decades. The majority of current clinical use involves diagnostic procedures, which use either positron-emission tomography (PET) or single-photon imaging to detect anatomic abnormalities that are difficult to visualize using conventional imaging techniques (e.g., MRI and X-ray). The potential of therapeutic radiometals has more recently been realized and relies on ionizing radiation to induce irreversible DNA damage, resulting in cell death. In both cases, radiopharmaceutical development has been largely geared toward the field of oncology; thus, selective tumor targeting is often essential for efficacious drug use. To this end, the rational design of fourcomponent radiopharmaceuticals has become popularized. This Review introduces fundamental concepts of drug design and applications, with particular emphasis on bifunctional chelators (BFCs), which ensure secure consolidation of the radiometal and targeting vector and are integral for optimal drug performance. Also presented are detailed accounts of production, chelation chemistry, and biological use of selected main group and rare earth radiometals.

show abstract

Section: Yttriummentioning

confidence: 99%

Radioactive Main Group and Rare Earth Metals for Imaging and Therapy

2018

View full text Add to dashboard Cite

show abstract

“…For the production of the positron emitter 86 Y (T½ = 14.7 h), the nuclear reactions references see [136]). Very recently the nuclear process 89 Y(p,4n) 86 Zr 86 Y has also been reported [137]. The method of choice for production of 86 Y, however, is the 86 Sr(p,n) 86 Y reaction on a highly enriched target, originally reported by the Jülich group [5,6].…”

Section: Theranostic Pair 86 Y/ 90 Ymentioning

confidence: 99%

New developments in the production of theranostic pairs of radionuclides

Qaim

Schölten

Neumaier

2018

J Radioanal Nucl Chem

132

View full text Add to dashboard Cite

A brief historical background of the development of the theranostic approach in nuclear medicine is given and seven theranostic pairs of radionuclides, namely 44g Sc/ 47 Sc, 64 Cu/ 67 Cu, 83 Sr/ 90 Sr, 86 Y/ 90 Y, 124 I/ 131 I, 152 Tb/ 161 Tb and 152 Tb/ 149 Tb, are considered. The first six pairs consist of a positron and a β −-emitter whereas the seventh pair consists of a positron and an α-particle emitter. The decay properties of all those radionuclides are briefly mentioned and their production methodologies are discussed. The positron emitters 64 Cu, 86 Y and 124 I are commonly produced in sufficient quantities via the (p,n) reaction on the respective highly enriched target isotope. A clinical scale production of the positron emitter 44g Sc has been achieved via the generator route as well as via the (p,n) reaction, but further development work is necessary. The positron emitters 83 Sr and 152 Tb are under development. Among the therapeutic radionuclides, 89 Sr, 90 Y and 131 I are commercially available and 161 Tb can also be produced in sufficient quantity at a nuclear reactor. Great efforts are presently underway to produce 47 Sc and 67 Cu via neutron, photon and charged particle induced reactions. The radionuclide 149 Tb is unique because it is an α-particle emitter. The present method of production of 152 Tb and 149 Tb involves the use of the spallation process in combination with an on-line mass separator. The role of some emerging irradiation facilities in the production of special radionuclides is discussed.

show abstract