Analysis of the excitation function of alpha-particle-induced reactions on natural silver

Abstract

Excitation functions of the reactions 107Ag[(α, n); (α, 2n); (α, αn); (α, α2n)] and,109Ag[(α, 2n); (α, 3n); (α, 4n); (α, α3n); (α, α4n)] were investigated up to 70 MeV by the stacked foil activation technique and Ge(Li) gamma-ray spectroscopy method. Since the natural silver used as the target has two odd mass stable isotopes of abundance 51.83% (107Ag) and 48.17% (109Ag), their activation in some cases gives the same residual nucleus through different reaction channels, but with very different Q values. In such cases, the individual reaction cross sections are separated with the help of the ratio of theoretical cross sections. The experimental cross sections were compared with the predictions of a pre-equilibrium hybrid model. The (α, xn) reactions are fairly well reproduced with initial exciton number n0 = 4(4p0h), whereas (α, αxn) reactions are underestimated in magnitude by a factor of five to six.

Investigation of alpha particle induced reactions on natural silver in the 40–50 MeV energy range

“…The new data in Fig. 9 show a good continuation to the previous results of Takács et al [10], lower than the data of Patel et al [8] and show a good agreement with the data of Wasilewsky et al [12], in spite of their energy shift. Both TENDL-2017 and EMPIRE 3.2 give completely different trends and values.…”

Recommended nuclear data for medical radioisotope production: diagnostic positron emitters

“…[291] The nine experimental datasets available in the literature are shown in Fig. 133 [178,278,[293][294][295][296][297][298][299] together with the TENDL calculations. Six datasets were rejected (Wasilevsky et al [295] (discrepant values), Misaelides and Münzel [294] (energy steps too large, can not be controlled), Chaubey et al [296] (values too high), Fukushima et al [293] (values Fig.…”

“…Six datasets were rejected (Wasilevsky et al [295] (discrepant values), Misaelides and Münzel [294] (energy steps too large, can not be controlled), Chaubey et al [296] (values too high), Fukushima et al [293] (values Fig. 133 Nine experimental datasets for the 107 Ag(α,n) 110m In reaction available in the literature [178,278,[293][294][295][296][297][298][299], and TENDL calculations Fig. 134 Three selected experimental datasets for the 107 Ag(α,n) 110m In reaction [178,278,299] with the Padé fit (L = 9, N = 32, χ 2 = 1.94, solid line) and estimated total uncertainties in percentages, including 4% systematic uncertainty (dashed line, right-hand scale) too low at higher energy), Patel et al [297] (values too low), Takács et al [298] (values too low)), and the remaining three sets were used in the statistical fitting procedure.…”

New cross section data and review of production routes of medically used 110mIn

“…Especially for the medically important 111 In, most frequently produced though the 112 Cd(p,2n) reaction with 24-25 MeV incident proton energy, the 109 Ag(α,2n) could be a real alternative production route, taking into account that the 111 In can be produced with high yields and low impurity levels. A large number of measurements were done for the 109 Ag(α,2n) 111 In reaction: Patel et al [44] Hasbroek et al [45], Ismail et al [46], Wasilewsky et …”