Journal of Radiation Safety and Measurement

Journal of Radiation Safety and Measurement

Study of the 199Au nanoparticles production parameters via irradiation of platinum target by using thermal neutrons

Document Type : Conference Paper

Authors
Amir Hosein Alinejad-Kamalabad 1
Tayeb Kakavand 1
Mohammadreza Aboudzadeh-Rovais 2
Saeed Kakaei 2
1 Department of Physics, Imam Khomeini International University, Qazvin, Iran
2 Radiation Application Research School, Nuclear Science and Technology Research Institute, Tehran, Iran
Abstract
In this study, the 199Au nanoparticles production parameters have been investigated by a two-part study. The first part is about the indirect method for production of non-carrier-added (NCA) 199Au radionuclide which was investigated both theoretically and experimentally. We applied MCNPX-2.6 code, TALYS-1.9, and ALICE code, aiming to simulate the reactor core of Tehran Research Reactor (TRR) and determining the activity of 199Au by MCNPX code using cross-sections calculated by TALYS-1.9 and specifying the production yield of 199Au. Also, the excitation function of 199Au was calculated via  reaction by TALYS-1.9 and ALICE/ASH-0.1 codes. As the corresponding experimental approach, we worked on the reactor production of 199Au by utilizing  thermal neutron flux through irradiation of natural Pt target for a specified irradiation time of 21 hours and 10 minutes in TRR. Regarding our facilities for evaluating the production yield, two samples of 11 mg and 15.5 mg natural Pt targets were bombarded in TRR. Because the natural Pt target, consists of five different stable isotopes (192Pt, 194Pt, 195mPt, 196Pt, 198Pt), some radionuclides as impurities will be produced during the reactor bombardment. So, using an enriched Pt target will increase the production yield together with a reduction of the impurity production. To separate 199Au radionuclide from the impurities mentioned above, and also to calculate both the chemical yield and the radionuclide purity of 199Au, two chemical separation techniques were applied. In the first technique, 199Au radionuclide was separated from impurities by employing liquid-liquid extraction (LLX) using ethyl acetate. As a result of this separation, the chemical yield of 199Au radionuclide was more than 99%. In the second technique, 199Au was separated by employing LLX using liquid cation exchanger, Di-(2-Ethylhexyl) phosphoric acid (HDEHP). By applying this technique, the chemical yield of 199Au radionuclide was more than 80% consequently. We calculated the theoretical findings and compared the results with the related experimental values. In the second part of the present study, the synthesis of radioactive 199Au nanoparticles (199AuNPs) have been investigated by the Turkevich method with the aim of produce citrate-gold nanoparticles with different sizes of approximately 50 nm. Possible uses and applications of 199Au nanoparticles in medicine are also discussed.
Keywords
Monte Carlo
yield
thermal neutrons radioisotope
199Au
nanoparticle
simulation
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