## 2 Cyclotron-Produced \({}^{68}\)Ga Using a Solid Target  
\({}^{68}\)Ga can be produced from solid targets using galvanized, pressed, foil, or molten targets. The irradiation parameters discussed were based on Advanced Cyclotron Systems, Inc. (ACSI) Richmond, Canada or GE Healthcare, Milwaukee, WI, USA cyclotrons. The introduction of pneumatic transfer systems, such as the QUANTUM Irradiation System(tm) (Vancouver, Canada), Solid Target Transfer ACSI (Richmond, Canada), and ALCEO Solid Target Processing System, COMECER (Castel Bolognese, Italy) was a critical development for \({}^{68}\)Ga production using solid target [32]. After the target irradiation, the target material is transferred to hot cells for dissolution with either concentrated hydrochloric acid (HCI) or nitric acid (HNO\({}_{3}\)). The separation of target material, purification, and formulation utilizing one-, two-, or three-column methods, making it possible to obtain high AMA in the shortest time at the end of purification (EOP) [22; 33; 34; 35; 36; 37; 38; 39]. ({}^{68}\)Ga Production Using a Solid Target in a Medical Scale PETtrace Cyclotron (GE Healthcare, Milwaukee, WI, USA)  
Previous experience with the GE PETtrace cyclotron has shown promising results [22; 32; 34; 38; 39], subsequently opening the possibility of distributing \({}^{68}\)Ga radio-pharmaceuticals to multiple centers. The setup shows a saturation yield and EOP of above 1 GBq/\(\mu\)A and 3.7 GBq, respectively, as displayed in Table 1.  
Figure 2: Steps in the production of the \({}^{68}\)Ga-labeled peptide from a medical cyclotron. \begin{table}
\begin{tabular}{c c c c c c c c} \hline \hline
**Target Preparation** & **Nominal Proton** & **Irradiation** & **EOB (GBq)** & \
\begin{tabular}{c} **Specific Activity** \\ **(GBq/ug)** \\ \end{tabular} &
\begin{tabular}{c} **Saturation Yield** \\ **(GBq/\mu A)** \\ \end{tabular} & **EOP (GBq)** & **Ref.** \\ \hline Target material: Electroplated on a platinum disc & 14.5 MeV & Current: 30 uA & 60.9 \(\pm\) 1.8 & NR & 2.72 \(\pm\) 0.08 & NR & [22] \\ Dimension: 7.0 mm & Time: 60 min & 60.9 \(\pm\) 1.8 & NR & 2.72 \(\pm\) 0.08 & NR & [22] \\ \(\delta\)Zn mass: 104: 1.27 & & & & & & \\ \hline Target material: Electroplated on a platinum backing & 14.5 MeV with 320 μm & Current: 35 uA & 6.3 \(\pm\) 0.4 & 2530 & 1.26 \(\pm\) 0.08 & 3.7 \(\pm\) 0.18 & [38] \\ Dimension: 10.0 mm & aluminium degdard foils & Time: 8.5 min & & & & \\ \(\delta\)Zn mass: 35.3 \(\pm\) 2.2 mg & & & & & & \\ \hline Target material: Electroplated & 13.0 MeV on target. & 100.0 mm & 100.0 mm & 100.0 mm & 100.0 mm & 100.0 mm & 100.0 mm & 100.0 mm \\ \(\delta\)Zn mass: 300 mg & & & & & & \\ \hline Target material: Full & 12.6 MeV with 500 μm & Current: 25 uA & 31 \(\pm\) 1 & 1209 \(\pm\) 18 & 2.48 \(\pm\) 0.06 & 18 \(\pm\) 2 & [34] \\ Dimension: 15.5 mm & aluminium energy degdard & Time: 68 min & & & & \\ \hline Target material: Electroplated on a silver backing & 13.0 MeV with 500 μm & Current: 80 uA & 370 & NR & 7.1 & 175.2 & [39] \\ Dimension: \(\sim\)10.0 mm & aluminum foil degdard & Time: 102 min & & & & \\ \hline \hline \end{tabular}
\end{table} 
Table 1: \({}^{96}\)Ga production with PETTrace Cyclotron with \({}^{96}\)Zn irradiation. Induded yield activity at EOB and EOP. The highest yield at the end of bombardment (EOB) was more than 370 GBq [32; 39]. Both studies recorded the same target material, current and nominal proton energy. However, [PERSON] and co-workers [32] used 28% more mass of enriched \({}^{68}\)Zn and a longer irradiation time than [PERSON] and group [39]. This was subsequently reflected in an increase in end-of-purification (EOP) activity of 18.8 GBq (approximately 10% more yield). For smaller-scale production, [PERSON] and co-authors [34] reported that their capacity to produce an EOB activity of 31 \(\pm\) 1 GBq \({}^{68}\)Ga with a respectable saturation yield of 2.48 \(\pm\) 0.06 GBq/\(\upmu\)A using a foil target with a dimension of 15.5 mm or a target mass of 40 mg, respectively.