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In view of several significant discrepancies in the excitation function of the  86 Sr(p,n) 86g+xm Y reaction which is the method of choice for the production of the non-standard positron emitter  86 Y 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  86 SrCO 3  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  nat Cu(p,xn) 62,63,65 Zn and  nat Ti(p,x) 48 V, 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  86 Y was calculated. Over the optimum production energy range E p  = 14 → 7 MeV the yield of  86 Y 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  86 Y obtained in clinical scale production runs. The levels of the isotopic impurities  87m Y,  87g Y, and  88 Y were also estimated and found to be &lt;2% in sum.

Accurate determination of production data of the non-standard positron emitter 86 Y via the 86 Sr(p,n)-reaction