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Whatever the radionuclide to be used in nuclear medicine, it is essential to know the expected yield during the production process, but also of all the possible radionuclidic impurities coproduced, that can have an impact on the product final quality, as well as in the related waste management. The availability of the majority of emerging radioisotopes, including the theranostic ones or pairs, is mainly limited by the fact that, for most of them, the optimal production route still needs to be strengthened if not defined in some cases. The aim of this work is to present a review on the charged particle induced nuclear cross sections to produce some emerging radionuclides for medical applications to show that all types of projectiles should be considered in the quest of producing medical radionuclides. An accurate analysis of the production routes is presented for some radionuclides (67Cu, 47Sc, 89Zr, 103Pd, 186gRe, 97Ru, 211At) chosen as examples to highlight (i) how the quality of the final product strongly depends on the chosen target/projectile/energy parameters set, (ii) how deuteron production routes may sometimes be more effective than the proton ones or lead to a different impurity profile and (iii) how α-particle beams may allow to bypass the limitations occurring when using Z = 1 beams. An overview of possible advantages and drawbacks of the cited production routes and of potential cross sections that still need to be measured, is also reported.

Despite its insufficient availability, Copper-67 is currently attracting much attention for its enormous potential for cancer therapy as theranostic radionuclide. This work aims to accurately measure the unexplored cross section 70Zn(p,x)67Cu in the energy range 45–70 MeV and to evaluate its potential advantages in the case of high-intensity proton beams provided by compact cyclotrons. Thin target foils of enriched 70Zn were manufactured by lamination at the INFN-LNL and irradiated at the ARRONAX facility using the stacked-foils method. A radiochemical procedure for the separation of Cu, Ga and Zn contaminants and the isolation of 67Cu from the irradiated material was developed. The efficiency of the chemical processing was determined for each foil by monitoring the activity of selected tracer radionuclides (61Cu, 66Ga and 69mZn) through γ-spectrometry. Experimental data of the 70Zn(p,x)67Cu, 64Cu, 67Ga, 66Ga, 69mZn, 65Zn cross sections were measured for the first time in the energy range 45–70 MeV and compared with the theoretical results obtained by using the TALYS code. The 67Cu production yield by using enriched 70Zn thick targets was compared with the results obtained by using 68Zn targets in the same irradiation conditions.

New data for the ${}^{\text{nat}}\mathrm{V}(p,x)$ reactions have been measured in the range 26--70 MeV, with production of the nuclides $^{47}\mathrm{Sc}, ^{43}\mathrm{Sc}, {}^{44m}\mathrm{Sc}, {}^{44g}\mathrm{Sc}, ^{46}\mathrm{Sc}, ^{48}\mathrm{Sc}, ^{42}\mathrm{K}, ^{43}\mathrm{K}, ^{48}\mathrm{V}, ^{48}\mathrm{Cr}, ^{49}\mathrm{Cr}$, and $^{51}\mathrm{Cr}$. The focus is on the production of $^{47}\mathrm{Sc}$, a ${\ensuremath{\beta}}^{\ensuremath{-}}$ emitter suitable for innovative radiotheranostic applications in nuclear medicine. The measured cross sections for this radionuclide and its contaminants are compared with the theoretical excitation functions calculated with the talys code. In view of novel radiopharmaceutical applications, it is essential to accurately describe these cross sections for the evaluation of yields, purities, and dose releases. Hence, we optimize the level-density parameters of the microscopic models in the talys code to obtain the best possible descriptions of the new data. We consider different irradiation conditions to estimate the production yields from the cross sections determined in this paper.

Cyclotron-based radionuclides production by using solid targets has become important in the last years due to the growing demand of radiometals, e.g., 68Ga, 89Zr, 43/47Sc, and 52/54Mn. This shifted the focus on solid target management, where the first fundamental step of the radiochemical processing is the target dissolution. Currently, this step is generally performed with commercial or home-made modules separated from the following purification/radiolabelling modules. The aim of this work is the realization of a flexible solid target dissolution system to be easily installed on commercial cassette-based synthesis modules. This would offer a complete target processing and radiopharmaceutical synthesis performable in a single module continuously. The presented solid target dissolution system concept relies on an open-bottomed vial positioned upon a target coin. In particular, the idea is to use the movement mechanism of a syringe pump to position the vial up and down on the target, and to exploit the heater/cooler reactor of the module as a target holder. All the steps can be remotely controlled and are incorporated in the cassette manifold together with the purification and radiolabelling steps. The performance of the device was tested by processing three different irradiated targets under different dissolution conditions.

This work deals with the new cross section data obtained for the natV(p,x)43Sc nuclear reaction. We focus on this specific channel because we found a significant discrepancy with a recent NIM B publication, reporting extensive data on activation cross-sections induced by proton-Vanadium collisions up to 65 MeV. Proton-irradiation and γ -spectrometry were performed at ARRONAX facility (Nantes, France) by means of activation of stacked-foils targets up to 70 MeV. Our new experimental values are compared with all the previous measurements and supported by the results obtained with the reaction codes FLUKA, EMPIRE and TALYS. A discussion is given about the possible origin of the observed discrepancy.

The LARAMED project, acronym for LAboratory of RAdioisotopes for MEDicine, is the new research infrastructure being established at the Legnaro National Laboratories (LNL), focused on the production of novel medical radionuclides, actually unavailable for the scientific community. This work presents the recent advancements of the LARAMED laboratories and bunkers in the SPES facility, where the 70-MeV high current proton cyclotron was installed in 2015 to perform not only fundamental nuclear physics studies but also research activities related to medical applications. The latest research outcomes on the production of the theranostic 67Cu and 47Sc radionuclides, obtained thanks to the Italian and international LARAMED network, are also summarized.

International audience; The goal of PASTA project (acronym for production with accelerator of$^{47}$Sc for theranostic applications) is the determination of excitation functions associated to several nuclear reactions, aimed at yielding the theranostic radionuclide$^{47}$Sc. This work reports the main results obtained by irradiating natural vanadium targets with proton beams up to 70 MeV. Particular care is also given to the co-production of$^{46}$Sc, the only isotopic contaminant with half-life longer than$^{47}$Sc. Experimental results are compared with theoretical studies by means of known nuclear reaction software tools that are publicly available.

Thin targets of isotopically enriched 48Ti metallic powder on Al foil substrates for the nuclear cross-section measurements were manufactured using the HIgh energy VIbrational Powders Plating method in vacuum. The target areal thickness of 0.2–2 mg/cm2 was achieved as measured by weighing as well as by Elastic Backscattering Spectroscopy (EBS) analysis. The quality of the targets, in particular the deposit uniformity, was evaluated by Scanning Electron Microscope (SEM) assisted by the Energy Dispersive Spectroscopy (EDS). The microstructure of the HIVIPP deposited targets was analyzed for the first time. SEM analysis showed that the coating microstructure was strongly related to the original powder microstructure. It was also observed that the coating was not a powder monolayer. The smaller powder particles, which were the first to move in the electric field, remained attached to the substrate and created the first layers of the deposit. Further layers of bigger particles were then attached to the first layer. The information about the deposit microstructure was utilized to model the EBS analysis results. The subset of the prepared 48Ti enriched targets was successfully used for the nuclear cross-section measurement campaign up to 40 MeV using the proton beam (115 nA) available at the C70 cyclotron in ARRONAX (Nantes, France).

We present a detailed map of the uranium distribution and its uncertainties in the Variscan Basement of Northeastern Sardinia (VBNS) at a scale 1:100,000. An area of 2100 km2 was investigated by means of 535 data points obtained from laboratory and in situ gamma-ray spectrometry measurements. These data volume corresponds to the highest sampling density of the European Variscides, aimed at studying the genetic processes of the upper crust potentially triggered by an enrichment of radiogenic heat-producing elements. For the first time the Kriging with Variance of Measurement Error method was used to assign weights to the input data which are based on the degree of confidence associated to the measurements obtained with different gamma-ray spectrometry techniques. A detailed tuning of the model parameters for the adopted Experimental Semi-Variogram led to identify a maximum distance of spatial variability coherent to the observed tendency of the experimental data. We demonstrate that the obtained uranium distribution in the VBNS, characterized by several calc-alkaline plutons emplaced within migmatitic massifs and amphibolite-facies metamorphic rocks, is an excellent benchmark for the study of 'hot' collisional chains. The uranium map of VBNS, and in particular the Arzachena minor pluton, confirms the emplacement model based on the recognition of the different petrological associations characterizing the Variscan magmatic processes in the Late Paleozoic. Furthermore, the presented model of the uranium content of the geological bedrock is a potential baseline for future mapping of radon-prone areas., 16 pages, 6 Figures, 1 Map

In the last years, the technology for producing the important medical radionuclide technetium-99m by cyclotrons has become sufficiently mature to justify its introduction as an alternative source of the starting precursor [99mTc][TcO4]- ubiquitously employed for the production of 99mTc-radiopharmaceuticals in hospitals. These technologies make use almost exclusively of the nuclear reaction 100Mo(p,2n)99mTc that allows direct production of Tc-99m. In this study, it is conjectured that this alternative production route will not replace the current supply chain based on the distribution of 99Mo/99mTc generators, but could become a convenient emergency source of Tc-99m only for in-house hospitals equipped with a conventional, low-energy, medical cyclotron. On this ground, an outline of the essential steps that should be implemented for setting up a hospital radiopharmacy aimed at the occasional production of Tc-99m by a small cyclotron is discussed. These include (1) target production, (2) irradiation conditions, (3) separation/purification procedures, (4) terminal sterilization, (5) quality control, and (6) Mo-100 recovery. To address these issues, a comprehensive technology for cyclotron-production of Tc-99m, developed at the Legnaro National Laboratories of the Italian National Institute of Nuclear Physics (LNL-INFN), will be used as a reference example.

The cross sections of the 68Zn(p,2p)67Cu, 68Zn(p,2n)67Ga and 68Zn(p,3n)66Ga reactions were measured at the ARRONAX facility by using the 70 MeV cyclotron, with particular attention to the production of the theranostic radionuclide 67Cu. Enriched 68Zn material was electroplated on silver backing and exposed to a low-intensity proton beam by using the stacked-foils target method. Since 67Cu and 67Ga radionuclides have similar half-lives and same γ-lines (they both decay to 67Zn), a radiochemical process aimed at Cu/Ga separation was mandatory to avoid interferences in γ-spectrometry measurements. A simple chemical procedure having a high separation efficiency (>99%) was developed and monitored during each foil processing, thanks to the tracer isotopes 61Cu and 66Ga. Nuclear cross sections were measured in the energy range 35–70 MeV by using reference reactions recommended by the International Atomic Energy Agency (IAEA) to monitor beam flux. In comparison with literature data a general good agreement on the trend of the nuclear reactions was noted, especially with latest measurements, but slightly lower values were obtained in case of 67Cu. Experimental results of the 68Zn(p,2p)67Cu, 68Zn(p,2n)67Ga and 68Zn(p,3n)66Ga reactions were also compared with the theoretical values estimated by using the software TALYS. The production yield of the theranostic radionuclide 67Cu was estimated considering the results obtained in this work.

Boron plays an important role in astrophysics and, together with lithium and beryllium, is a probe of stellar structure during the pre-main sequence and main-sequence phases. In this context, the 10 B(p,α )7 Be reaction is of particular interest.The literature data show discrepancies in the energy range between 100 keV and 2 MeV. This also poses a normalization problem for indirect data obtained with the Trojan Horse Method.A new measurement of the 10 B(p,α )7 Be reaction cross section was performed at Legnaro National Laboratories (LNL). At LNL, the cross section was determined with the activation technique by measuring the activated samples at a low-background counting facility. The analysis of that experiment is now complete and the results are here presented.

In this paper we present maps of K, eU, and eTh abundances of Elba Island (Italy) obtained with a multivariate spatial interpolation of airborne {\gamma}-ray data using the constraints of the geologic map. The radiometric measurements were performed by a module of four NaI(Tl) crystals of 16 L mounted on an autogyro. We applied the collocated cokriging (CCoK) as a multivariate estimation method for interpolating the primary under-sampled airborne {\gamma}-ray data considering the well-sampled geological information as ancillary variables. A random number has been assigned to each of 73 geological formations identified in the geological map at scale 1:10,000. The non-dependency of the estimated results from the random numbering process has been tested for three distinct models. The experimental cross-semivariograms constructed for radioelement-geology couples show well-defined co-variability structures for both direct and crossed variograms. The high statistical correlations among K, eU, and eTh measurements are confirmed also by the same maximum distance of spatial autocorrelation. Combining the smoothing effects of probabilistic interpolator and the abrupt discontinuities of the geological map, the results show a distinct correlation between the geological formation and radioactivity content. The contour of Mt. Capanne pluton can be distinguished by high K, eU and eTh abundances, while different degrees of radioactivity content identify the tectonic units. A clear anomaly of high K content in the Mt. Calamita promontory confirms the presence of felsic dykes and hydrothermal veins not reported in our geological map. Although we assign a unique number to each geological formation, the method shows that the internal variability of the radiometric data is not biased by the multivariate interpolation., Comment: 43 pages, 9 figures, 5 tables. In Remote Sensing of Environment (2013)

In this paper, we report an extensive survey of the natural radioactive content of rocks of the Tuscany Region (Italy): this permitted the first total natural radioactivity map of the region. The sampling was planned using the geological map of Tuscany at scale 1:250,000, which contains 45 distinct geological groups recognized by tectonic and stratigraphic features. Each geological group was characterized for the total activity by measuring the activity concentrations of 40K, 238U and 232Th in 865 samples using a high-purity germanium (HPGe) gamma-ray spectrometer. The average areal distribution of samples is approximately one sample per 25 km2. The radiometric map was constructed through the reclassification of each geological formation based on the median value of the total activity. Seven classes of total activity are identified by choosing percentiles almost evenly spread across the range of values. This map represents the starting point for future studies on natural background radiation, geochemical ...

Automated !-ray spectrometer for monitoring wastes made by nonnuclear industries XHIXHA G.1, BEZZON G.P.1, BROGGINI C.2, BUSO G.P.1, CACIOLLI A.2, CALLEGARI I.3, COLONNA T.3, FIORENTINI G.1, GUASTALDI E.3, KACELI XHIXHA M.4, MANTOVANI F.5, MASSA G.3, MENEGAZZO R.2, MOU L.1 ROSSI ALVAREZ AND C.2 AND STRATI V.5 1Legnaro National Laboratory (LNL-INFN), Via dell’Universita, 2 35020 Legnaro, Padova, Italy – (xhixha@fe.infn.it) 2Padova Section INFN, Via Marzolo 8 35131 Padova, Italy – (carlo.broggini@pd.infn.it ) 3CGT Center for GeoTechnologies, University of Siena, Via Vetri Vecchi, 34 52027 S. GiovanniValdarno, Italy – ()callegari@unisi.it 4University of Sassari, Botanical, Ecological and Geological Sciences Department, Piazza Universita 2107100 Sassari, Italy – (mxhixha@fe.infn.it ) 5University of Ferrara, Physics Department, Via Saragat, 1 44100 Ferrara, Italy – (mantovani@fe.infn.it )

The $^{10}$B(p,$\alpha$)$^{7}$Be reaction is of great interest since it has many applications in different fields of research such as nuclear astrophysics, nuclear physics, and models of new reactors for clean energy generation. This reaction has been studied at the AN2000 accelerator of the INFN National Laboratories of Legnaro (LNL). The total cross section has been measured in a wide energy range (250 $-$ 1182 keV) by using the activation method. The decays of the $^7$Be nuclei produced by the reaction were measured at the low counting facility of LNL by using two fully shielded high-purity germanium detectors. The present dataset shows a large discrepancy with respect to one of the previous data at the same energies and reduces the total uncertainty to the level of 6\%. An R-matrix calculation has been performed on the present data using the parameters from previous Trojan Horse measurements for the 10 and 500 keV resonances. The present data do not lay on the R-matrix fit in one point suggesting the existence of a $^{11}$C level not observed yet. Further nuclear investigations are needed to confirm this hypothesis., Comment: accepted to EPJA (6 pages, 3 figures)

Materials containing radionuclides of natural origin, which is modified by human made processes and being subject to regulation because of their radioactivity are known as NORM. We present a brief review of the main categories of non-nuclear industries together with the levels of activity concentration in feed raw materials, products and waste, including mechanisms of radioisotope enrichments. The global management of NORM shows a high level of complexity, mainly due to different degrees of radioactivity enhancement and the huge amount of worldwide waste production. The future tendency of guidelines concerning environmental protection will require both a systematic monitoring based on the ever-increasing sampling and high performance of gamma ray spectroscopy. On the ground of these requirements a new low background fully automated high-resolution gamma-ray spectrometer MCA_Rad has been developed. The design of Pb and Cu shielding allowed to reach a background reduction of two order of magnitude with respect to laboratory radioactivity. A severe lowering of manpower cost is obtained through a fully automation system, which enables up to 24 samples to be measured without any human attendance. Two coupled HPGe detectors increase the detection efficiency, performing accurate measurements on sample volume (180 cc) with a reduction of sample transport cost of material. Details of the instrument calibration method are presented. MCA_Rad system can measure in less than one hour a typical NORM sample enriched in U and Th with some hundreds of Bq/kg, with an overall uncertainty less than 5%. Quality control of this method has been tested. Measurements of certified reference materials RGK-1, RGU-2 and RGTh-1 containing concentrations of K, U and Th comparable to NORM have been performed, resulting an overall relative discrepancy of 5% among central values within the reported uncertainty., 21 pages, 4 figures, 6 tables

An increasing demand of environmental radioactivity monitoring comes both from the scientific community and from the society. This requires accurate, reliable and fast response preferably from portable radiation detectors. Thanks to recent improvements in the technology, $\gamma$-spectroscopy with sodium iodide scintillators has been proved to be an excellent tool for in-situ measurements for the identification and quantitative determination of $\gamma$-ray emitting radioisotopes, reducing time and costs. Both for geological and civil purposes not only $^{40}$K, $^{238}$U, and $^{232}$Th have to be measured, but there is also a growing interest to determine the abundances of anthropic elements, like $^{137}$Cs and $^{131}$I, which are used to monitor the effect of nuclear accidents or other human activities. The Full Spectrum Analysis (FSA) approach has been chosen to analyze the $\gamma$-spectra. The Non Negative Least Square (NNLS) and the energy calibration adjustment have been implemented in this method for the first time in order to correct the intrinsic problem related with the $\chi ^2$ minimization which could lead to artifacts and non physical results in the analysis. A new calibration procedure has been developed for the FSA method by using in situ $\gamma$-spectra instead of calibration pad spectra. Finally, the new method has been validated by acquiring $\gamma$-spectra with a 10.16 cm x 10.16 cm sodium iodide detector in 80 different sites in the Ombrone basin, in Tuscany. The results from the FSA method have been compared with the laboratory measurements by using HPGe detectors on soil samples collected in the different sites, showing a satisfactory agreement between them. In particular, the $^{137}$Cs isotopes has been implemented in the analysis since it has been found not negligible during the in-situ measurements., Comment: accepted by Science of Total Environment: 8 pages, 10 figures, 3 tables

The production of innovative radionuclides in the context of theranostics is currently a topic of great interest. Various INFN projects are underway in search of new data and new techniques for radionuclides production. Among the possible channels under study, recent developments indicate 67Cu and 47Sc as good candidates competitive with more traditional nuclides, thanks to their application both for diagnostic and for therapy. INFN recently started two projects for the measurement of proton-induced reactions, considering the forthcoming use of the high-performance cyclotron installed at INFN-LNL (70 MeV maximum energy): COME in CSN3 (2016) and PASTA in CSN5 (Young Researchers grants 2016). The knowledge of reaction cross sections at low-intermediate energies is crucial in this context and, in parallel to the need of new measurements, it is important also to review the current situation in the reaction-model simulation of the production yields, by using the existing and available nuclear reaction codes. In particular the FLUKA code, based on the PEANUT (Pre-Equilibrium Approach to Nuclear Thermalisation) model, was used to calculate the production of residual nuclei in different experiments and is already validated with data. In this study we use FLUKA to calculate the reaction cross sections for the production of copper and scandium isotopes at the energy of interest for the LARAMED project (10–100 MeV). A comparison of the results obtained with dedicated codes (Talys and Empire) and with available experimental data is also given.

This study focuses on the radiological characterisation of building materials manufactured in Albania by using a high-resolution gamma-ray spectrometer. The average activity concentrations of (40)K, (226)Ra and (232)Th were, respectively, 644.1±64.2, 33.4 ± 6.4 and 42.2 ± 7.6 Bq kg(-1) in the clay brick samples and 179.7 ± 48.9, 55.0 ± 5.8 and 17.0 ± 3.3 Bq kg(-1) in the cement samples. The calculated activity concentration index (ACI), varied from 0.48±0.02 to 0.63±0.04 in the clay brick samples and from 0.29±0.03 to 0.37±0.02 in the cement samples. Based on the ACI, all of the clay brick and cement samples were categorised as A1 materials. The authors can exclude (at 3σ level) any restriction of their use as bulk materials.