A novel method for radiochemical separation of radioyttrium from Sr targets using precipitation technique

Sadeghi, Mahdi; Zali, A.; Avila, M.J.

doi:10.1524/ract.2010.1737

Cited by 15 publications

(8 citation statements)

References 10 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…64 Cu, 86 Y, 89 Zr and 124 I, will certainly increase. The same may be true for other potentially useful positron emitters, such as 55 Co, 71 As, 72 As and 73 Se. If the demands for those radionuclides increase further, it may become incumbent to intensively search for intermediate energy production routes leading to higher yields and purity.…”

Section: Research Orientationsmentioning

confidence: 86%

“…Although the expected yield of 64 Cu via the latter reaction is higher, the availability of only lowenergy deuterons at medical cyclotrons has precluded the use of this reaction for production purposes. On the other hand, small amounts of 64 Cu have been produced using a deuteron induced reaction on 64 86 Y involve: (a) coprecipitation with La(OH) 3 followed by ion-exchange separation of radioyttrium from bulk lanthanum [47,48], (b) electrolysis [49][50][51], (c) multiple column chromatography [52], (d) solvent extraction [53] and (e) simple precipitation of the target element [54,55]. Out of those processes, the electrolytic method appears to be more promising.…”

Section: Novel Positron Emittersmentioning

confidence: 99%

See 1 more Smart Citation

The present and future of medical radionuclide production

Qaim

2012

Radiochimica Acta

100

View full text Add to dashboard Cite

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.

show abstract

Section: Research Orientationsmentioning

confidence: 86%

Section: Novel Positron Emittersmentioning

confidence: 99%

The present and future of medical radionuclide production

Qaim

2012

Radiochimica Acta

100

View full text Add to dashboard Cite

show abstract

“…Four other methods of separation have also been applied: one involves electrolysis [59,90,91], the other one multiple column chromatography [60], the third one solvent extraction [cf . 61], and the fourth one a simple precipitation of the target material [62,92]. The electrolytic method appears to be more promising.…”

Section: Production Using Low-energy Reactionsmentioning

confidence: 99%

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

Qaim¹

2011

Ract

View full text Add to dashboard Cite

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.

show abstract

“…The commercial availability of this isotope is limited. The chemical separation of 86 Y from 86 Sr targets has been a subject of quite a few studies each of those adressed facility specific applications and limitations (Aardaneh et al, 2006;Avila-Rodriguez et al, 2008;Finn et al, 1999;Garmestani et al, 2002;Lukic et al, 2009;Park et al, 2004;Reischl et al, 2002;Rosch et al, 1993b;Sadeghi et al, 2010;van der Meulen et al, 2009). Since we also have reported the separation of Y from strontium chloride targets irradiated at BLIP previously (Medvedev et al, 2011;Medvedev et al, 2012b), this paper is only focused on production yields 2 and radioisotopic purity of the yttrium fraction as a function of energy incident on 86 SrCl 2 .…”

Section: Introductionmentioning

confidence: 99%

Tailoring medium energy proton beam to induce low energy nuclear reactions in 86SrCl2 for production of PET radioisotope 86Y

Medvedev

Mausner

Pile

2015

Applied Radiation and Isotopes

View full text Add to dashboard Cite

This paper reports results of experiments at Brookhaven Linac Isotope Producer (BLIP) aiming to investigate effective production of positron emitting radioisotope (86)Y by the low energy (86)Sr(p,n) reaction. BLIP is a facility at Brookhaven National Laboratory designed for the proton irradiation of the targets for isotope production at high and intermediate proton energies. The proton beam is delivered by the Linear Accelerator (LINAC) whose incident energy is tunable from 200 to 66 MeV in approximately 21 MeV increments. The array was designed to ensure energy degradation from 66 MeV down to less than 20 MeV. Aluminum slabs were used to degrade the proton energy down to the required range. The production yield of (86)Y (1.2+/-0.1 mCi (44.4+/-3.7) MBq/μAh) and ratio of radioisotopic impurities was determined by assaying an aliquot of the irradiated (86)SrCl2 solution by gamma spectroscopy. The analysis of energy dependence of the (86)Y production yield and the ratios of radioisotopic impurities has been used to adjust degrader thickness. Experimental data showed substantial discrepancies in actual energy propagation compared to energy loss calculations.

show abstract

A novel method for radiochemical separation of radioyttrium from Sr targets using precipitation technique

Cited by 15 publications

References 10 publications

The present and future of medical radionuclide production

The present and future of medical radionuclide production

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

Tailoring medium energy proton beam to induce low energy nuclear reactions in 86SrCl2 for production of PET radioisotope 86Y

Contact Info

Product

Resources

About