Alternative method for 64Cu radioisotope production

Le, Van So; Howse, J.; Zaw, Myo Myint; Pellegrini, Paul A.; Katsifis, Andrew; Greguric, Ivan; Weiner, R.T.

doi:10.1016/j.apradiso.2009.02.069

Cited by 21 publications

(11 citation statements)

References 13 publications

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“…This procedure to remove nickel was proposed by several authors [11,12,14,17,18], but in their processes a second purification step on another column was necessary to separate copper from cobalt impurities [12,17,18] or nickel from cobalt [14]. In our case, we use the fact that copper complexes are stronger than cobalt complexes and an adjustment of HCl concentration allows a selective elution of cobalt.…”

Section: Resultsmentioning

confidence: 85%

“…In the literature, one finds different procedures that use Chelex-100 resin [17,18]. Matarrese et al [17] used one resin Chelex-100 to purify copper; they, however, gave no information concerning the potential impurities of cobalt.…”

Section: Resultsmentioning

confidence: 98%

“…Matarrese et al [17] used one resin Chelex-100 to purify copper; they, however, gave no information concerning the potential impurities of cobalt. Le et al [18] used two different columns, a first one which is a strong anionic resin Brought to you by | New York University Bobst Library Technical Services Authenticated Download Date | 5/31/15 4:34 AM AG1 × 4, essentially to discard nickel and a second one which is a chelating resin Chelex-100 to improve cobaltcopper separation. The only way to achieve a good separation with only one chromatographic column seems to be by using chloride ions in order to play with the complexation properties of the different metals.…”

Section: Resultsmentioning

confidence: 99%

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One step purification process for no-carrier-added ⁶⁴Cu produced using enriched nickel target

Alliot¹,

Michel

Bonraisin

et al. 2011

Ract

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Copper-64 has found many applications in positron emission tomography (PET). Its half-life allows to use it for dosimetric studies associated to copper-67 targeted radiotherapy in cancer treatment. The use of 64 Ni( p, n) 64 Cu nuclear reaction is known to produce 64 Cu in large amount and with a high specific activity. In this study, targets were obtained by electroplating onto a gold backing and a typical target irradiation uses 200 nA, 17 MeV protons during 30 min. After irradiation, pure copper-64 is obtained using only one chromatographic column. Nickel-64 is removed in a first elution step and cobalt isotopes in a second one. The extraction yield for copper-64 is 92 ± 3% and nickel and cobalt impurities are under the detection limit. A recovery process of nickel-64 has also been developed.

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Section: Resultsmentioning

confidence: 85%

Section: Resultsmentioning

confidence: 98%

Section: Resultsmentioning

confidence: 99%

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One step purification process for no-carrier-added ⁶⁴Cu produced using enriched nickel target

Alliot¹,

Michel

Bonraisin

et al. 2011

Ract

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“…The production route 64 Ni( p, n) 64 Cu, originally suggested by the Jülich group [14], has been further developed in several other laboratories [cf . [45][46][47][48][49][50]. In a recent work sophisticated targetry calculations have been done [50].…”

Section: Production Using Low-energy Reactionsmentioning

confidence: 99%

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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“…The separation of 64 Cu is generally done via anion-exchange chromatography. A recent work [36] describes sophisticated targetry calculations. Due to increasing demand for this radionuclide in radioimmunotherapy, presently a commercialization of this production process is being pursued.…”

Section: Novel Positron Emittersmentioning

confidence: 99%

The present and future of medical radionuclide production

Qaim

2012

Radiochimica Acta

100

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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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Alternative method for 64Cu radioisotope production

Cited by 21 publications

References 13 publications

One step purification process for no-carrier-added ⁶⁴Cu produced using enriched nickel target

One step purification process for no-carrier-added ⁶⁴Cu produced using enriched nickel target

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

The present and future of medical radionuclide production

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Alternative method for 64Cu radioisotope production

Cited by 21 publications

References 13 publications

One step purification process for no-carrier-added 64Cu produced using enriched nickel target

One step purification process for no-carrier-added 64Cu produced using enriched nickel target

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

The present and future of medical radionuclide production

Contact Info

Product

Resources

About

One step purification process for no-carrier-added ⁶⁴Cu produced using enriched nickel target

One step purification process for no-carrier-added ⁶⁴Cu produced using enriched nickel target