Monte Carlo simulation and experimental studies of the production of neutron-rich medical isotopes using a particle accelerator

The developments of nuclear medicine lead to an increasing demand for the production of radioisotopes with suitable nuclear and chemical properties. Furthermore, from the literature it is evident that the production of radioisotopes using charged-particle accelerators instead of nuclear reactors is gaining increasing popularity. The main advantages of producing medical isotopes with accelerators are carrier free radionuclides of short lived isotopes, improved handling, reduction of the radioactive waste, and lower cost of isotope fabrication. Proton-rich isotopes are the result of nuclear interactions between enriched stable isotopes and energetic protons. An interesting observation is that during the production of proton-rich isotopes, fast and intermediately fast neutrons from nuclear reactions such as (p,xn) are also produced as a by-product in the nuclear reactions. This observation suggests that it is perhaps possible to use these neutrons to activate secondary targets for the production of neutron-rich isotopes. The study of secondary radioisotope production with fast neutrons from (p,xn) reactions using a particle accelerator is the main goal of the research in this thesis.;Yttrium-90 (90Y) is a good example of an isotope that can be made in combination with proton-rich isotope production. Traditionally, 90Y is obtained from a 90Sr/90Y generator. In order to produce a carrier free isotope, a chemical separation of 90Sr must be performed. The main disadvantage of 90Sr is a high toxicity level. 90Sr is well known to cause bone marrow suppressions, and it has a long half-life of 28.78 y. Therefore, special waste handling and storage conditions are required.;In this study, 90Y has been produced with (p,xn) fast neutrons using the 90Zr(n,p)90Y reaction. Fast neutrons for the activation process were produced during proton irradiation of natural tungsten targets. The proton beam used was produced by a 33 MeV linear accelerator (LINAC). Since 90Y is a pure beta emitter, the gamma-rays from the 90Zr(n,2n)89Zr reaction were used to quantify the incident neutron flux of the 90Zr sample. The experimental results of the 89Zr activity were compared with simulation data that are based on Monte Carlo calculations. The simulation codes, Cascade Exciton Model (CEM 95) and Monte Carlo N-Particle system (MCNPX) were used to calculate the angular and energy distribution of neutrons incident in the Zr target. Based on the MCNPX and CEM neutron flux predictions, the 90Y activity was estimated.