Excitation functions of (α,xn) reactions on natRb and natSr from threshold up to 26MeV: Possibility of production of 87Y, 88Y and 89Zr

Kandil, S. A.; Spahn, Ingo; Schölten, B.; Saleh, Z.A.; Saad, Shokry M.; Coenen, Heinz H.; Qaim, S.M.

doi:10.1016/j.apradiso.2006.12.007

Cited by 37 publications

(10 citation statements)

References 12 publications

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“…Now a study on the nat Rb(α, xn) 88 Y process is described. The numerical data and a detailed discussion of the results are given elsewhere [14]. An overview of the measured excitation functions is given in Fig.…”

Section: Y (T 1/2 = 10665 D)mentioning

confidence: 99%

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Nuclear data for production of ⁸⁸Y, ¹⁴⁰Nd, ¹⁵³Sm and ¹⁶⁹Yb via novel routes

Qaim¹,

Spahn²,

Kandil³

et al. 2007

Radiochimica Acta

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Therapeutic radionuclide / Nuclear reaction / Cross section / Excitation function / Integral yield / Radionuclidic puritySummary. The possibilities of production of the therapyrelated radionuclides 140 Nd, 153 Sm and 169 Yb, and of 88 Y, in no-carrier-added form were investigated. For 88 Y production the nuclear processes nat Sr( p, xn) 88 Y and nat Rb(α, xn) 88 Y over the energy ranges E p = 14 → 9 MeV and E α = 18 → 12 MeV, respectively, can be utilised, although the former reaction is superior, both in terms of yield and radionuclidic purity. For 140 Nd production the reactions 141 Pr( p, 2n) 140 Nd and nat Ce( 3 He, xn) 140 Nd were investigated in detail. The optimum energy ranges are E p = 30 → 15 MeV and E3 He = 35 → 20 MeV, respectively. Both processes yield high-purity 140 Nd. The former reaction, however, leads to a product yield about 17 times higher than the latter reaction, and is therefore to be preferred. In the case of 153 Sm, investigations were done on the 153 Eu(n, p) 153 Sm reaction with 14 MeV d(Be) neutrons as well as on the 150 Nd(α, n) 153 Sm reaction. The yield of the (n, p) reaction is very low, but the (α, n) reaction over the energy range E α = 25 → 15 MeV offers a good potential for production of no-carrier-added 153 Sm in quantities sufficient for therapeutic applications. Also for the radionuclide 169 Yb a novel route, viz. 169 Tm( p, n) 169 Yb reaction, was investigated. A critical comparison of this route with the commonly used (n, γ ) route, however, showed that, due to the much higher cost involved, the ( p, n) process should be utilised only when there is a real need of the high specific radioactivity product.

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Section: Y (T 1/2 = 10665 D)mentioning

confidence: 99%

“…Evidently, for production purposes the former route is to be preferred. [14]). The suitable energy range for the production of 88 Y is shown as a shaded area.…”

Section: Y (T 1/2 = 10665 D)mentioning

confidence: 99%

Nuclear data for production of ⁸⁸Y, ¹⁴⁰Nd, ¹⁵³Sm and ¹⁶⁹Yb via novel routes

Qaim¹,

Spahn²,

Kandil³

et al. 2007

Radiochimica Acta

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“…The radionuclide 87g Y (T 1/2 = 79.8 h; E c = 388.5 keV (82.2%) and E c = 484.8 keV (89.8%)) used as a c-ray emitter can be used in combination with the single photon emission computed tomography [7]. The long-lived 88g Y (T 1/2 = 106.63 d; E c = 898.04 keV (93.7%) and E c = 1836.06 keV (99.2%)) radionuclide is used to investigate slow metabolic processes in animals [8] and also frequently used as a calibration source of c-ray detectors. The 88 Zr radionuclide can be used to produce significant amount of 88 Y radioisotope through the 88 Zr/ 88 Y generator.…”

Section: Introductionmentioning

confidence: 99%

Measurement of excitation functions in alpha-induced reactions on yttrium

Shahid

Kim

Naik

et al. 2015

Nuclear Instruments and Methods in Physics Research Section B:

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Y(a,x) reactions MC-50 cyclotron Stacked-foil activation technique Excitation functionOff line c-ray spectrometry a b s t r a c tThe excitation functions of 89g,m,90,91m,92m Nb, 88,89 Zr, and 87g,m,88,90m,91m Y from alpha-induced reactions on 89 Y were measured from their respective threshold to 45 MeV by using a stacked-foil activation technique at the MC-50 cyclotron of the Korean Institute of Radiological and Medical Sciences. The results were compared with the earlier reported data as well as with the theoretical values obtained from the TENDL-2013 library based on the TALYS1.6 code. Our measurements in the energy region from the threshold energy to 45 MeV are in general good agreement with the other experimental data and calculated results. The integral yields for thick target of the produced radionuclides were also deduced from their measured cross sections and the stopping power of 89 Y. The measured excitation functions find importance in various practical applications including nuclear medicine and improvement of nuclear model calculations.

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“…In case of non-availability of 40 MeV protons, the utility of the 70 Ge(α, n) 73 Se reaction in the production of 73 Se in GBq amounts has also been demonstrated [31]. The use of the nat Cu(α, x) 66 Ga and nat Sr(α, x) 89 Zr reactions to produce 66 Ga and 89 Zr is again optional [115,133], since the yields of the commonly used 66 Zn( p, n) 66 Ga and 89 Y( p, n) 89 Zr processes are much higher. The possibility of production of 82 Sr via the 82 Kr(α, 4n) 82 Sr reaction has also been investigated [126].…”

Section: Production Using Intermediate Energy Reactionsmentioning

confidence: 95%

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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Excitation functions of (α,xn) reactions on natRb and natSr from threshold up to 26MeV: Possibility of production of 87Y, 88Y and 89Zr

Cited by 37 publications

References 12 publications

Nuclear data for production of ⁸⁸Y, ¹⁴⁰Nd, ¹⁵³Sm and ¹⁶⁹Yb via novel routes

Nuclear data for production of ⁸⁸Y, ¹⁴⁰Nd, ¹⁵³Sm and ¹⁶⁹Yb via novel routes

Measurement of excitation functions in alpha-induced reactions on yttrium

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

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Excitation functions of (α,xn) reactions on natRb and natSr from threshold up to 26MeV: Possibility of production of 87Y, 88Y and 89Zr

Cited by 37 publications

References 12 publications

Nuclear data for production of 88Y, 140Nd, 153Sm and 169Yb via novel routes

Nuclear data for production of 88Y, 140Nd, 153Sm and 169Yb via novel routes

Measurement of excitation functions in alpha-induced reactions on yttrium

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

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Product

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Nuclear data for production of ⁸⁸Y, ¹⁴⁰Nd, ¹⁵³Sm and ¹⁶⁹Yb via novel routes

Nuclear data for production of ⁸⁸Y, ¹⁴⁰Nd, ¹⁵³Sm and ¹⁶⁹Yb via novel routes