No description available.

Made available in DSpace on 2014-10-09T12:25:41Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:03:41Z (GMT). No. of bitstreams: 1 06873.pdf: 3893215 bytes, checksum: 6d198b442dc331f7ee99c5eb2cd23c10 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2014-10-09T12:25:41Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:03:41Z (GMT). No. of bitstreams: 1 06873.pdf: 3893215 bytes, checksum: 6d198b442dc331f7ee99c5eb2cd23c10 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2014-10-09T12:50:56Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:02:52Z (GMT). No. of bitstreams: 1 11105.pdf: 5490789 bytes, checksum: e5c917b212eb27dee51d17f19d0021db (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2014-10-09T12:54:07Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:09:24Z (GMT). No. of bitstreams: 1 12435.pdf: 4820144 bytes, checksum: 0d8279d9b23571886f63adee62a8b6f4 (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Quimica, Universidade de Sao Paulo - IQ/USP

Made available in DSpace on 2014-10-09T12:50:56Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:02:52Z (GMT). No. of bitstreams: 1 11105.pdf: 5490789 bytes, checksum: e5c917b212eb27dee51d17f19d0021db (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2014-10-09T12:54:07Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:09:24Z (GMT). No. of bitstreams: 1 12435.pdf: 4820144 bytes, checksum: 0d8279d9b23571886f63adee62a8b6f4 (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Quimica, Universidade de Sao Paulo - IQ/USP

<p> The use of high flux research reactors, such as the High Flux Isotope Reactor (HFIR), to produce a wide variety of both industrial and medical isotopes has been well documented and proven to be economically feasible. However, due to the lack of access to these high flux facilities by most countries, isotope production methods utilizing reactors with low to moderate flux levels are needed, especially for short lived medical isotopes whose production must be relatively close to the location where they will be administered. In recent years medical isotopes that can both be used for treatment and diagnostic uses have become of great interest. One of the most popular of these theragnostic radionuclides is lutetium-177. Production of high-grade Lu-177 can be achieved in both high and low flux reactors through two different production methods. The current work looks to determine the feasibility of producing Lu-177 via the indirect route, using the relatively low flux of PUR-1. This will be accomplished through the use of high-fidelity models and simulations to predict the resulting production rates of the desired products. The results of these models and simulations will then be compared to the results obtained from the experimental irradiation of various samples of ytterbium oxide in PUR-1. Many studies have successfully produced Lu-177 using moderate and high flux reactors and several papers have studied the predicted production rate for low to moderate flux reactors by using the reported thermal flux of various research reactors and the reported cross-section values for ytterbium. A Monte Carlo based model of PUR-1 will be developed to determine the radiative capture reaction rates for the ytterbium targets across all neutron energies. This model in conjunction with a simplified MATLAB model, to solve the series of partial differential equations describing the production and decay of each product isotope, will be used to predict isotope production rates and will be compared to experimentally obtained results. </p>

The e-linac beam that will serve the ARIEL Electron Target East (AETE) has an energy range from 30 MeV to 50 MeV with a power up to 500 kW. The beam electrons are to be converted into photons by means of an electron-to-gamma converter with the purpose of inducing photonuclear reactions in a target to produce exotic isotopes. In the process of conversion, the primary electron beam power deposition in the converter causes a significant increase of the temperature that must be dissipated. The converter performance contributes notably to the overall isotope production and extraction efficiency. This thesis describes the work to optimize and verify the conceptual design of the electron-to-gamma converter through simulations and experimental measurements. / Graduate

Made available in DSpace on 2014-10-09T12:46:45Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:56:46Z (GMT). No. of bitstreams: 1 08358.pdf: 3987174 bytes, checksum: bd5e0ea6705a189997deab3c68d85291 (MD5) / Fundação de Amparo à Pesquisa do Estado de São Paulo (FAPESP) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP / FAPESP:99/08249-9