The flow rate of coolant and the particle beam current are important when high beam current irradiations are intended for production of radionuclides. The beam current on natCu target to produce 63Zn ...via the natCu(p,n)63Zn reaction was investigated and the beam current was obtained more than 350 μA that is the maximum allowed beam current used for producing medical radioisotopes in Nuclear Science and Technology Research Institute of Iran. In addition, the temperature distribution on the target under the different cooling water flow rates has been simulated based on finite element analysis program. The results show that the cooling water flow rate can be brought down to 1.5 L/min without the risk of melting of target material and boiling water.
•The beam current on natCu target to produce 63Zn via the natCu(p,n)63Zn reaction has been numerically analyzed.•The optimum thickness of natCu target is calculated from the nuclear cross-section data and SRIM-2013 calculation.•The highest proton current to produce 63Zn radionuclide was estimated.•To determine the optimal design of the target, the distribution of temperature was calculated using the COMSOL program.
Background: The thermoluminescent dosimeter (TLD) and Monte Carlo (MC) dosimetry are carried out to determine the occupational dose for personnel in the handling of 125I seed sources. Materials and ...Methods: TLDs were placed in different layers of the Alderson-Rando phantom in the thyroid, lung and also eyes and skin surface. An 125I seed source was prepared and its activity was measured using a dose calibrator and was placed at two distances of 20 and 50 cm from the Alderson-Rando phantom. In addition, the Monte Carlo N-Particle Extended (MCNPX 2.6.0) code and a computational phantom with a lattice-based geometry were used for organ dose calculations. Results and Discussion: The comparison of TLD and MC results in the thyroid and lung is consistent. Although the relative difference of MC dosimetry to TLD for the eyes was between 4% and 13% and for the skin between 19% and 23%, because of the existence of a higher uncertainty regarding TLD positioning in the eye and skin, these inaccuracies can also be acceptable. The isodose distribution was calculated in the cross-section of the head phantom when the 125I seed was at two distances of 20 and 50 cm and it showed that the greatest dose reduction was observed for the eyes, skin, thyroid, and lungs, respectively. The results of MC dosimetry indicated that for near the head positions (distance of 20 cm) the absorbed dose rates for the eye lens, eye and skin were 78.1±2.3, 59.0±1.8, and 10.7±0.7 µGy/mCi/hr, respectively. Furthermore, we found that a 30 cm displacement for the 125I seed reduced the eye and skin doses by at least 3- and 2-fold, respectively. Conclusion: Using a computational phantom to monitor the dose to the sensitive organs (eye and skin) for personnel involved in the handling of 125I seed sources can be an accurate and inexpensive method.
The 63Zn was produced by16.8 MeV proton irradiation of natural copper. Thick target yield for 63Zn in the energy range of 16.8 →12.2 MeV was 2.47 ± 0.12 GBq/μA.h. Reasonable agreement between ...achieved experimental data and theoretical value of thick target yield for 63Zn was observed. A simple separation procedure of 63Zn from copper target was developed using cation exchange chromatography. About 88 ± 5% of the loaded activity was recovered. The performance of FLUKA to reproduce experimental data of thick target yield of 63Zn is validated. The achieved results from this code were compared with the corresponding experimental data. This comparison demonstrated that FLUKA provides a suitable tool for the simulation of radionuclide production using proton irradiation.
•The production of 63Zn radionuclide via natCu(p,n)63Zn reaction using 16.8 MeV protons was studied.•Thick-target yield of 2.47 ± 0.12 GBq/μA.h was experimentally obtained for 63Zn.•A simple separation procedure was developed to separate 63Zn radionuclide from copper target.•The thick target yield of 63Zn was evaluated using FLUKA code.•The simulated results have been compared with the experimental and theoretical data.
A useful approach to optimize of radioisotope production is the use of Monte Carlo simulations prior to experimentation. In this paper, the GEANT4 code was employed to calculate the saturation yields ...of 62,63Zn from proton-induced reactions of natural copper, enriched 63Cu and 65Cu. In addition, the saturation yields of the investigated radio-nuclides were calculated using the stopping power from the SRIM-2013 and reported experimental data for cross sections. The simulated saturation yields were compared with experimental values. Good agreement between the experimental and corresponding simulated data demonstrated that GEANT4 provides a suitable tool for radionuclide simulation production using proton irradiation.
The .sup.63Zn is an important positron emitting radionuclide for using in PET. The theoretical models, TALYS-1.6 and EMPIRE-3.2.2, were used to construct the excitation functions for proton, ...deuteron, and alpha particle induced reactions on different targets. The results were compared with the reported experimental data and with the theoretical values obtained from the TENDL-2014 database. Stopping powers were calculated using SRIM 2013 code for each reaction. The .sup.63Zn production yields were estimated using calculated cross sections and stopping powers. It has been verified that .sup.63Cu(p,n).sup.63Zn reaction is the optimum .sup.63Zn production route.
The
63
Zn is an important positron emitting radionuclide for using in PET. The theoretical models, TALYS-1.6 and EMPIRE-3.2.2, were used to construct the excitation functions for proton, deuteron, ...and alpha particle induced reactions on different targets. The results were compared with the reported experimental data and with the theoretical values obtained from the TENDL-2014 database. Stopping powers were calculated using SRIM 2013 code for each reaction. The
63
Zn production yields were estimated using calculated cross sections and stopping powers. It has been verified that
63
Cu(p,n)
63
Zn reaction is the optimum
63
Zn production route.
Excitation functions and theoretical yields via charge particle induced reactions were evaluated using EMPIRE-3.2.2 and ALICE/ASH codes and the obtained results have been discussed and compared with ...the available reported experimental data. It has been verified that .sup.natCu(p,n).sup.65Zn reaction is the optimum .sup.65Zn production route. The .sup.65Zn was produced using .sup.natCu(p,xn) .sup.65Zn reaction in the energy range of 16.8 right arrow 12.2 MeV with the thick target yield of 0.15 ± 0.005 MBq/muA h. The .sup.65Zn radionuclide was purified by anion exchange chromatography.
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