As the number of patients suffering from different cancers has been increased, researchers have evaluated several ways to diagnose and treat these abnormalities. In this regard, application of radionuclides is an interesting option through which some cancers can be simultaneously diagnosed and treated. Radionuclides used in medicine can be produced through nuclear reactors, linear accelerators, generators, fission and fusion.

⁶⁴Cu is one of the most useful radionuclide as a theranostic agent with γ, β⁺ and β^– decay (E.C. (43.53%), β^– (38.48%) and β⁺ (17.52%); End-point E_β⁺ = 653 keV, End-point E_β^– = 579 keV, Eg=1345.84 keV, I_γ = 0.47%) and also 12.7 h half-life making it an interesting option in Positron Emission Tomography (PET) imaging and targeted endoradiotherapy. ⁶⁴Cu can be produced with ⁶³Cu(n,g)⁶⁴Cu and ⁶⁴Zn(n,p)⁶⁴Cu reactions in nuclear reactor. Another copper radionuclide is ⁶⁷Cu with γ and β^– decay (E _{mean β}^– = 141 keV) , E_γ = 184 keV (46.7%), 93 keV (16.60%), 91 keV (7.26%)) and 2.576 days half-life which is useful in radioimmunotherapy, Single Photon Emission Computed Tomography (SPECT) imaging and tracer kinetic studies. It can be produced with ⁶⁷Zn(n,p)⁶⁷Cu reaction. The decay schematic of ⁶⁴Cu and ⁶⁷Cu is shown in Figure 1.

Fig. 1. The decay scheme of ⁶⁴Cu and ⁶⁷Cu radionuclides.

The present study examined these reactions with ^natZnO, ^natZnO nanoparticles (NPs), ^natCu and ^natCu-NPs targets in Tehran Research Reactor (TRR) for ⁶⁴Cu and ⁶⁷Cu radionuclides productions. Radioactive nanoparticles enjoy the ability of having several radioactive atoms. The prepared samples were inserted in one of the irradiation box of nuclear reactor core with the significant thermal and fast neutron flux about 30 minutes.  After cooling times, the irradiated samples were pulled out from the reactor core and prepared for gamma spectrometry with a high purity p-type detector (HPGe). The production yields were also assessed with HPGe detector.

Theoretical calculation of radionuclide production yields required consideration of several different physical parameters such as reaction cross section, radiation time, half-time and neutron flux. Cross section parameters were calculated with benefit nuclear codes such as TALYS-1.8 (the last update). The production yields of ⁶⁴Cu and ⁶⁷Cu were calculated using MCNP code which needs to simulate the reactor core of TRR with a maximum power of 5 MW, pool type with 9×6 grid plate containing cool fuel elements, radiation box and etc. This reactor is designed for research, train and production of radionuclides. The theoretical and experimental production yields were compared to each other which showed a good agreement between them. Therefore, MCNPX can be used to optimize radionuclide production condition in the nuclear reactor. On the other hand, comparing the experimental production yields with nano target showed insignificant changes.

Zahra Karimi ¹, Mahdi Sadeghi ², Mostafa Jalilifar ^2
1Department of Medical Radiation Engineering, Faculty of Advanced Sciences and Technologies, University of Isfahan, Isfahan, Iran
²Medical Physics Department, School of Medicine, Iran University of Medical Sciences, P.O. Box: 14155-6183, Tehran, Iran

Publication

64Cu, a powerful positron emitter for immunoimaging and theranostic: Production via natZnO and natZnO-NPs.
Karimi Z, Sadeghi M, Mataji-Kojouri N
Appl Radiat Isot. 2018 Jul

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