Excitation functions of proton induced nuclear reactions on enriched 61Ni and 64Ni: Possibility of production of no-carrier-added 61Cu and 64Cu at a small cyclotron

Szelecsényi, F.; Blessing, G.; Qaim, S.M.

doi:10.1016/0969-8043(93)90172-7

Cited by 202 publications

(178 citation statements)

References 14 publications

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“…The commonly used production method in each case is the low-energy ( p, n) reaction on the respective highly-enriched target nucleus. The basic data in all three cases were measured at the Forschungszentrum Jülich [40][41][42]. Although extensive development work related to targetry and chemical separation of those radionuclides has been done in many laboratories (for review cf.…”

Section: Non-standard Positron Emittersmentioning

confidence: 99%

New trends in nuclear data research for medical radionuclide production

Qaim

2013

Radiochimca Acta

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Medical radionuclide / Optimisation of production route / Nuclear reaction cross section / Standardisation of data / Alternative routes for production of 99m Tc and 68 Ga / Non-standard positron emitter / Novel therapeutic radionuclide Summary. Nuclear reaction cross section data are of great significance in optimisation of production routes of radionuclides. This article deals with some newer aspects of data research related to production of both standard and novel radionuclides. The recent work to standardise the known data is discussed and new measurements with regard to further optimisation of production routes of some commonly used radionuclides are mentioned. Attempts to increase the specific activity of some reactor-produced radionuclides through the use of charged-particle induced reactions are outlined. The jeopardy in the supply of 99m Tc via a fission-produced 99 Mo/ 99m Tc generator is considered and its possible direct production at a cyclotron is briefly discussed. Regarding the novel radionuclides, development work is presently focussed on non-standard positron emitters for diagnosis and on low-range highly ionising radiation emitters for internal radiotherapy. Recent nuclear reaction cross section measurements related to the production of the two types of radionuclides are briefly reviewed and some anticipated trends in nuclear data research are considered.

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Section: Non-standard Positron Emittersmentioning

confidence: 99%

New trends in nuclear data research for medical radionuclide production

Qaim

2013

Radiochimca Acta

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“…Large activities of 61 Cu can be produced via the 61 Ni(p,n) 61 Cu reaction using a highly enriched nickel target [4]. The major advantage for this production route is the ability to achieve high specific activities 61 Cu and the use of the convenient production energy range (E p = 10.5-10.3MeV) of a standard biomedical cyclotron [6]. A disadvantage of this pathway is the high cost of the enriched 61 Ni.…”

Section: Introductionmentioning

confidence: 99%

“…The radiometal copper-61 ( 61 Cu; E + mean range = 0.242-0.527MeV) can be used to label bioactive molecules for positron emission tomography (PET) imaging [6]. Several studies have employed 61 Cu for studying hypoxia (e.g.…”

Section: Introductionmentioning

confidence: 99%

Cyclotron production of [sup 61]Cu using natural Zn & enriched [sup 64]Zn targets

Ali

Smith

Chan

et al. 2012

AIP Conference Proceedings

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Abstract. Copper-61 ( 61 Cu) shares with 64 Cu certain advantages for PET diagnostic imaging, but has a shorter half-life (3.4hr vs. 12.7hr) and a greater probability of positron production per disintegration (61% vs. 17.9%). One important application is for in vivo imaging of hypoxic tissue. In this study 61 Cu was produced using the 64 Zn(p,D) 61 Cu reaction on natural Zn or enriched 64 Zn targets. The enriched 64 Zn (99.82%) was electroplated onto high purity gold or silver foils or onto thin Al discs. A typical target bombardment used 30PA; at 11.7, 14.5 or 17.6MeV over 30-60min. The 61 Cu (radiochemical purity of >95%) was separated using a combination of cation and anion exchange columns. The 64 Zn target material was recovered after each run, for re-use. In a direct comparison with enriched 64 Zn-target results, 61 Cu production using the cheaper nat Zn target proved to be an effective alternative.

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“…Fur- Ni(p,n) 64 Cu nuclear reaction. This cyclotron reaction requires a proton beam of about 11 MeV and presents a good production yield with a cross section of about 700 mbarn [15,16]. With the ARRONAX cyclotron (a high energy and high intensity multi-particle accelerator located in Nantes, France) another reaction route, 64 Ni (d,2n), is used.…”

Section: Introductionmentioning

confidence: 99%