A simple thick target for production of 89Zr using an 11 MeV cyclotron

Link, Jeanne; Krohn, Kenneth A.; O’Hara, Matthew J.

doi:10.1016/j.apradiso.2017.01.037

Cited by 21 publications

(8 citation statements)

References 17 publications

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“…According to the modeling results, which are in good agreement with the published experimental data, 89 Y(p,n) 89 Zr reaction is considered to be the best for producing zirconium-89, and optimum energy for proton bombardment is 14 MeV [21,22,23,24]. The reaction can be successfully performed using small biomedical cyclotrons (<20 MeV); even 11 MeV cyclotrons are suitable [25,26,27].…”

Section: Introductionsupporting

confidence: 68%

Preparation of Zirconium-89 Solutions for Radiopharmaceutical Purposes: Interrelation Between Formulation, Radiochemical Purity, Stability and Biodistribution

et al. 2019

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Zirconium-89 is a promising radionuclide for nuclear medicine. The aim of the present work was to find a suitable method for obtaining zirconium-89 solutions for radiopharmaceutical purposes. For this purpose, the ion exchange behavior of zirconium-89 solutions was studied. Radio-TLC (thin layer chromatography) and biodistribution studies were carried out to understand speciation of zirconium-89 complexes and their role in the development of new radiopharmaceuticals. Three methods of zirconium-89 isolation were studied using ZR (hydroxamate) and Chelex-100 resins. It was found that ZR-resin alone is not enough to obtain stable zirconium-89 formulations. An easy and effective method of reconstitution of [89Zr]Zr-oxalate to [89Zr]Zr-citrate using Chelex-100 resin was developed. Developed procedures allow obtaining [89Zr]Zr-oxalate (in 0.1 M sodium oxalate solution) and [89Zr]Zr-citrate (in 0.1–1.0 M sodium citrate solution). These solutions are perfectly suitable and convenient for radiopharmaceutical purposes. Our results prove [89Zr]Zr-citrate to be advantageous over [89Zr]Zr-oxalate. During evaluation of speciation of zirconium-89 complexes, a new TLC method was developed, since it was proved that there is no comprehensive method for analysis or zirconium-89 preparations. The new method provides valuable insights about the content of “active” ionic form of zirconium-89. The interrelation of the chromatographic behavior of zirconium-89 preparations and their biodistribution was studied.

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Section: Introductionsupporting

confidence: 68%

Preparation of Zirconium-89 Solutions for Radiopharmaceutical Purposes: Interrelation Between Formulation, Radiochemical Purity, Stability and Biodistribution

et al. 2019

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“…The 100% natural abundance of the 89 Y target decreases side reactions and minimizes production cost. Using 89 Y metal targets, typical yields range from 12 to 61 MBq (0.32–1.6 mCi)/μAh . More recently, pressed yttrium oxide powder targets as well as targets containing a solution of 89 Y(NO 3 ) 3 have been assessed as alternatives to solid targets and provided promising alternative routes to the synthesis of isotopically pure 89 Zr.…”

Section: Zirconiummentioning

confidence: 99%

“…Using 89 Y metal targets, typical yields range from 12 to 61 MBq (0.32−1.6 mCi)/μAh. 122 More recently, pressed yttrium oxide powder targets as well as targets containing a solution of 89 Y(NO 3 ) 3 have been assessed as alternatives to solid targets and provided promising alternative routes to the synthesis of isotopically pure 89 Zr. One advantage of a pressed salt or solution target is elimination or simplification of the target dissolution step after irradiation.…”

Section: Radionuclide Productionmentioning

confidence: 99%

Radioactive Transition Metals for Imaging and Therapy

2018

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Nuclear medicine is composed of two complementary areas, imaging and therapy. Positron emission tomography (PET) and single-photon imaging, including single-photon emission computed tomography (SPECT), comprise the imaging component of nuclear medicine. These areas are distinct in that they exploit different nuclear decay processes and also different imaging technologies. In PET, images are created from the 511 keV photons produced when the positron emitted by a radionuclide encounters an electron and is annihilated. In contrast, in single-photon imaging, images are created from the γ rays (and occasionally X-rays) directly emitted by the nucleus. Therapeutic nuclear medicine uses particulate radiation such as Auger or conversion electrons or β − or α particles. All three of these technologies are linked by the requirement that the radionuclide must be attached to a suitable vector that can deliver it to its target. It is imperative that the radionuclide remain attached to the vector before it is delivered to its target as well as after it reaches its target or else the resulting image (or therapeutic outcome) will not reflect the biological process of interest. Radiochemistry is at the core of this process, and radiometals offer radiopharmaceutical chemists a tremendous range of options with which to accomplish these goals. They also offer a wide range of options in terms of radionuclide half-lives and emission properties, providing the ability to carefully match the decay properties with the desired outcome. This Review provides an overview of some of the ways this can be accomplished as well as several historical examples of some of the limitations of earlier metalloradiopharmaceuticals and the ways that new technologies, primarily related to radionuclide production, have provided solutions to these problems.

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“…There are several established and potential medical radioisotopes among Mo, Nb and Zr elements, such as 99 Mo, 93m Mo (Sadeghi et al, 2010), 95g Nb (Matthews and Molinaro, 1962), 90g Nb (Milad and Mahdi, 2011) and 89g Zr (see e.g. (Link et al, 2017) and references therein). Investigations on reactions to produce such radioisotopes are still insufficient and additional efforts are required (Capote et al, 2017).…”

Section: Introductionmentioning

confidence: 99%

Production cross sections of Mo, Nb and Zr radioisotopes from α-induced reaction on natZr

Murata

Aikawa

Saito

et al. 2019

Applied Radiation and Isotopes

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Cross sections of α-induced reactions on natural zirconium were measured up to 50 MeV using the stacked-foil technique, activation method and high resolution γ-ray spectrometry. The production cross sections of 93m,99 Mo, 90g,92m,95g,95m,96 Nb and 88,89g,95 Zr were determined and compared with other experimental data measured earlier and result of theoretical calculations. The integral thick target yield of 99 Mo was deduced from the measured cross section data.

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A simple thick target for production of 89Zr using an 11 MeV cyclotron

Cited by 21 publications

References 17 publications

Preparation of Zirconium-89 Solutions for Radiopharmaceutical Purposes: Interrelation Between Formulation, Radiochemical Purity, Stability and Biodistribution

Preparation of Zirconium-89 Solutions for Radiopharmaceutical Purposes: Interrelation Between Formulation, Radiochemical Purity, Stability and Biodistribution

Radioactive Transition Metals for Imaging and Therapy

Production cross sections of Mo, Nb and Zr radioisotopes from α-induced reaction on natZr

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