Accurate determination of production data of the non-standard positron emitter 86Y via the 86Sr(p,n)-reaction
| Autor: | Jonathan T. Morrell, Haleema Zaneb, Ingo Spahn, Andrew S. Voyles, M. Shamsuzzhoha Basunia, Stefan Spellerberg, Jesus A. Rios, L. A. Bernstein, Sándor Sudár, M. Shuza Uddin, Bernd Neumaier, Syed M. Qaim, Bernhard Scholten |
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| Rok vydání: | 2020 |
| Předmět: |
Nuclear reaction
Analytical chemistry nuclear model calculation Flux Induced radioactivity 010403 inorganic & nuclear chemistry 01 natural sciences 030218 nuclear medicine & medical imaging Inorganic Chemistry 03 medical and health sciences 0302 clinical medicine integral yield and isotopic purity of the product Gamma spectroscopy ddc:610 Irradiation Physical and Theoretical Chemistry Excitation function cross section (SrCO3)-Sr-86 thin sample Chemistry proton irradiation 0104 chemical sciences excitation function Yield (chemistry) Inorganic & Nuclear Chemistry Excitation |
| Zdroj: | Radiochimica acta 108(9), 747-756 (2020). doi:10.1515/ract-2020-0021 Radiochimica Acta, vol 108, iss 9 |
| ISSN: | 2193-3405 0033-8230 |
| DOI: | 10.1515/ract-2020-0021 |
| Popis: | In view of several significant discrepancies in the excitation function of the 86Sr(p,n)86g+xmY reaction which is the method of choice for the production of the non-standard positron emitter 86Y for theranostic application, we carried out a careful measurement of the cross sections of this reaction from its threshold up to 16.2 MeV at Forschungszentrum Jülich (FZJ) and from 14.3 to 24.5 MeV at LBNL. Thin samples of 96.4% enriched 86SrCO3 were prepared by sedimentation and, after irradiation with protons in a stacked-form, the induced radioactivity was measured by high-resolution γ-ray spectrometry. The projectile flux was determined by using the monitor reactions natCu(p,xn)62,63,65Zn and natTi(p,x)48V, and the calculated proton energy for each sample was verified by considering the ratios of two reaction products of different thresholds. The experimental cross section data obtained agreed well with the results of a nuclear model calculation based on the code TALYS. From the cross section data, the integral yield of 86Y was calculated. Over the optimum production energy range Ep = 14 → 7 MeV the yield of 86Y amounts to 291 MBq/μA for 1 h irradiation time. This value is appreciably lower than the previous literature values calculated from measured and evaluated excitation functions. It is, however, more compatible with the experimental yields of 86Y obtained in clinical scale production runs. The levels of the isotopic impurities 87mY, 87gY, and 88Y were also estimated and found to be |
| Databáze: | OpenAIRE |
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