Nuclear reactions of Ga69 and Ga71 with 13–56 MeV protons

Chemical radioanalysis of production of positron-emitting radioisotope Gallium-68 via (p,n) and (p,2n) reactions using compact cyclotron for tomography applications

In this study, the proton-induced reactions of 68Zn and 69Ga aimed at generating 68Ga were simulated and modeled using Talys code and neural network software. In the first step, both targets were simulated under different proton energies and at different bombardments times to generate a total of six thousand data. Then, the obtained data from the Talys, including the various cross-sections, contaminations, the main product i.e. 68Ga, and other options were completely saved in the output file. Afterwards, the inputs of the neural network were selected from the output of the Talys by analyzing and considering most of the key features. A total of four inputs, two of which are different energies related to the reaction, the other is the process sequence and the fourth input is the bombardment time, were recognized as suitable inputs and the model was trained differently depending on the type of target. The selected model was a feed-forward neural network with 5 nodes in a middle layer, which was able to estimate the output of Talys code by changing the input parameters with extremely high accuracy. Two different models including the main model for estimating the output of the main sample (product) and the sub-model for estimating process pollution or impurity were trained, and then the trained model was tested on the deduced process data. The implementation results fully demonstrated the high accuracy of the method. The neural network model is much easier to implement than the Talys code, and its execution speed is very high. In addition, it can be used appropriately as a system alternative for optimization and different structures in medical and biological engineering.

67Cu Production Capabilities: A Mini Review

Is the ⁶⁷Cu production worldwide feasible for expanding preclinical and clinical studies? How can we face the ingrowing demands of this emerging and promising theranostic radionuclide for personalized therapies? This review looks at the different production routes, including the accelerator- and reactor-based ones, providing a comprehensive overview of the actual ⁶⁷Cu supply, with brief insight into its use in non-clinical and clinical studies. In addition to the most often explored nuclear reactions, this work focuses on the ⁶⁷Cu separation and purification techniques, as well as the target material recovery procedures that are mandatory for the economic sustainability of the production cycle. The quality aspects, such as radiochemical, chemical, and radionuclidic purity, with particular attention to the coproduction of the counterpart ⁶⁴Cu, are also taken into account, with detailed comparisons among the different production routes. Future possibilities related to new infrastructures are included in this work, as well as new developments on the radiopharmaceuticals aspects.

Characterization of SnO2-based (68)Ge/ (68)Ga generators and (68)Ga-DOTATATE preparations: radionuclide purity, radiochemical yield and long-term constancy

Background

With the increasing utilization of ⁶⁸Ge-⁶⁸Ga radionuclide generators, ⁶⁸Ga labelled peptides like DOTATATE are receiving more attention in nuclear medicine. On the one hand, the long half-life of the parent nuclide ⁶⁸Ge is an enormous advantage for routine applications, but the question of the long-term stability of the ⁶⁸Ge breakthrough arises, which up to now has scarcely been investigated.

Method

A sum of 123 eluates from four different ⁶⁸Ge-⁶⁸Ga generators (iThemba Labs, Faure, South Africa) and 115 samples of the prepared radiopharmaceutical ⁶⁸Ga-DOTATATE were measured first with a dose calibrator and again after decay of the eluted ⁶⁸Ga via gamma-ray spectrometry. A complete decay curve was recorded for one sample eluate. A further three eluates were eluted in ten fractions of 0.5 ml in order to obtain detailed information concerning the distribution of the two nuclides within the eluates. The influences of factors such as the amount of DOTATATE, addition of Fe³⁺ salts and replacement of HEPES buffer with sodium acetate on the radiochemical synthesis were also tested.

Results

The content of long-lived ⁶⁸Ge breakthrough increases over the entire period of use to more than 100 ppm. The labelling process with the chelator DOTA removes ⁶⁸Ge efficiently. The maximum activity found in the residues of the radiopharmaceuticals investigated in this study was below 10 Bq in nearly all cases. In many cases (12% of the labelled substance), the long-lived parent nuclide could not be identified at all. The labelling process is still viable for reduced amounts of the chelator and with acetate buffer.

Conclusion

Effective doses received by the patient from ⁶⁸Ge in the injected radiopharmaceutical ⁶⁸Ga-DOTATATE are lower than 0.1 μSv and are therefore practically negligible, especially when compared with the contribution of the PET radiopharmaceutical itself. Gamma-ray spectrometry as recommended by the European Pharmacopeia is suitable for quantification of radionuclidic impurities.

Electronic supplementary material

The online version of this article (doi:10.1186/s13550-014-0036-4) contains supplementary material, which is available to authorized users.

68Ge/68Ga production revisited: excitation curves, target preparation and chemical separation – purification

Targets withstanding high beam power for production of 68Ge by proton irradiation of Ga were developed using electrodeposition of Ga/Ni alloy (70/30%) on thick Cu backings. Cross sections for reactions, induced by protons (up to 36MeV) and deuterons (up to 50MeV), producing γ-emitting radioisotopes with half-lives longer than 2 h were measured in a stacked-foil irradiation using thin Ga/Ni targets produced with this technique. Excitation functions for 68,69Ge are discussed, relative to the monitor reactions natCu(p, x)62Zn or natAl(d, x)24,22Na. The results are compared to the scarce literature values. From derived thick target yields, optimal energy domain and batch yields for 68Ge production were calculated and contamination (from 69Ge and 71Ge) is discussed. A PC-controlled, automated dissolution and separation chemistry set-up for delivery of nca 69Ge was developed (yield about 90%) and implemented in an industrial system ready to be mounted in a hot cell.

Some nuclear chemical aspects of medical generator nuclide production at the Los Alamos hot cell facility

Generator nuclides constitute a convenient tool for applications in nuclear medicine. In this paper, some radiochemical aspects of generator nuclide parents regularly processed at Los Alamos are introduced. The bulk production of the parent nuclides68Ge,82Sr,109Cd and88Zr using charged particle beams is discussed. Production nuclear reactions for these radioisotopes, and chemical separation procedures are presented. Experimental processing yields correspond to 80%-98% of the theoretical thick target yield. Reaction cross sections are modeled using the code ALICE-IPPE; it is observed that the model largely disagrees with experimental values for the nuclear processes treated. Radionuclide production batches are prepared 1-6 times yearly for sales. Batch activities range from 40 MBq to 75 GBq.

Cross-section measurements of the nuclear reactions natZn(d,x)64Cu, 66Zn(d,alpha)64Cu and 68Zn(p,alphan)64Cu for production of 64Cu and technical developments for small-scale production of 67Cu via the 70Zn(p,alpha)67Cu process

The radionuclides 64Cu (T1/2=12.7h) and 67Cu (T1/2=61.9h) are useful in internal therapy. In connection with production of 64Cu, excitation functions of the reactions natZn(d,x)64Cu, 66Zn(d,alpha)64Cu and 68Zn(p,alphan)64Cu were measured radiochemically using the stacked-foil technique. From the measured data, the thick target yields of 64Cu were calculated and compared with experimental data available in the literature. The three investigated processes are discussed in comparison to the commonly used 64Ni(p,n)64Cu reaction for the production of 64Cu. As regards 67Cu production, the technical feasibility of the 70Zn(p,alpha)67Cu process was investigated. An electroplated isotopically enriched 70Zn target was developed which can withstand slanting beams of 20MeV protons of currents up to 20 microA. Methods for chemical separation of 67Cu and efficient recovery of the enriched target material were worked out. The method is suitable only for small-scale production of 67Cu.