The need of a stable production of At-211 is necessary to continue research in alpha-particle targeted radionuclide therapy. Our objectives were to establish the production of Astatine-211 at Texas A&M Cyclotron Institute, optimize the production methods to reduce the generation of contaminants and maximize At-211 production, and assess the radiological safety aspects of At-211 production. The production of the alpha-particle emitting radionuclide At-211 was performed at the Texas A&M Cyclotron Institute using the K500 superconducting cyclotron following the production reaction Bi-209(α, 2n)At-211 using a thick bismuth target of 500 μm. We carried out two irradiation experiments where the initial energy of the alpha-particle beam, 80 MeV, was degraded using multiple copper and aluminum foils to 27.8 and 25.3 MeV, respectively. The end of beam time was 4 hours for both experiments. The resulting At-211 yields were 36.0 and 12.4 MBq/μA-h, respectively. Several impurities were produced using the 27.8 MeV, which included At-210 and Po-210. However, when the 25.3 MeV beam was used, the impurities At-210 and Po-210 were resolved and other contaminants were minimized to less than 0.8% of At-211 yield. The production yields were in accordance to previous published results. From the success of these initial experiments, additional steps were taken to produce At-211 in excess quantities for distillation purposes. In order to obtain viable quantities of At-211, the gross yield needed to be increased due to losses that are incurred during distillation and radioactive decay. The ability to produce high yields of this isotope required a redesign of the target and use of the K150 cyclotron using a higher beam intensity.

The most promising applications for targeted alpha-therapy with astatine-211 (At-211) include treatments of disseminated microscopic disease, the major medical problem for cancer treatment. The primary advantages of targeted alpha-therapy with At-211 are that the alpha-particle radiation is densely ionizing, translating to high relative biological effectiveness (RBE), and short-range, minimizing damage to surrounding healthy tissues. In addition, theranostic imaging with I-123 surrogates has shown promise for developing new therapies with At-211 and translating them to the clinic. Currently, Canada does not have a way of producing At-211 by conventional methods because it lacks alpha-particle accelerators with necessary beam energy and intensity. The work presented here was aimed at studying the Rn-211/At-211 generator system as an alternative production strategy by leveraging TRIUMF's ability to produce rare isotopes. Recognizing that TRIUMF provided production opportunities for a variety of astatine isotopes, this work also originally hypothesized and evaluated the use of At-209 as a novel isotope for preclinical Single Photon Emission Computed Tomography (SPECT) with applications to At-211 therapy research. At TRIUMF's Isotope Separator and Accelerator (ISAC) facility, mass separated ion beams of short­-lived francium isotopes were implanted into NaCl targets where Rn-211 or At-209 were produced by radioactive decay, in situ. This effort required methodological developments for safely relocating the implanted radioactivity to the radiochemistry laboratory for recovery in solution. For multiple production runs, Rn-211 was quantitatively transferred from solid NaCl to solution (dodecane) from which At-211 was efficiently extracted and evaluated for clinical applicability. This validated the use of dodecane for capturing Rn-211 as an elegant approach to storing and shipping Rn-211/At-211 in the future. Po-207 contamination (also produced by Rn-211 decay) was removed using a granular tellurium (Te) column before proceeding with biomolecule labelling. Although the produced quantities were small, the pure At-211 samples demonstrated these efforts to have a clear path of translation to animal studies. For the first time in history, SPECT/CT was evaluated for measuring At-209 radioactivity distributions using high energy collimation. The spectrum detected for At-209 by the SPECT camera presented several photopeaks (energy windows) for reconstruction. The 77-90 Po X­-ray photopeak reconstructions were found to provide the best images overall, in terms of resolution/contrast and uniformity. Collectively, these experiments helped establish guidelines for determining the optimal injected radioactivity, depending on scan parameters. Moreover, At-209-based SPECT demonstrated potential for pursuing image-­based dosimetry in mouse tumour models, in the future. Simultaneous SPECT imaging with At-209 and I-123 was demonstrated to be feasible, supporting the future evaluation of At-209 for studying/validating I-123 surrogates for clinical image-based At-211 dosimetry. This work also pursued a novel strategy for labelling cancer targeting peptides with At-211, using octreotate (TATE, a somatostatin analogue for targeting tumour cells, mostly neuroendocrine tumours) prepared with or without N-terminus PEGylation (PEG2), followed by conjugation with a closo-decaborate linking moiety (B10) for attaching At-211. Binding affinity and in vivo biodistributions for the modified peptides were determined using iodine surrogates. The results indicated that B10-PEG2-TATE retained target binding affinity but that the labelling reaction with iodine degraded this binding affinity significantly, and although having high in vivo stability, no I-123-B10-PEG2-TATE tumour uptake was observed by SPECT in a mouse tumour model positive for the somatostatin receptor (sstr2a). This suggested that further improvements are required for labelling. A new method for producing At-211 at TRIUMF is established, and At-209-­based SPECT imaging is now demonstrated as a new preclinical technology to measure astatine biodistributions in vivo for developing new radiopharmaceuticals with At-211. Combined with the theranostic peptide labelling efforts with iodine, these efforts provide a foundation for future endeavours with At-211-­based alpha-therapy at TRIUMF. All procedures were performed safely and rapidly, suitable for preclinical evaluations. All animal studies received institutional ethics approval from the University of British Columbia (UBC). / Graduate

Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2016-08-25T11:05:49Z No. of bitstreams: 0 / Made available in DSpace on 2016-08-25T11:05:49Z (GMT). No. of bitstreams: 0 / A radioimunoterapia (RIT) faz uso de anticorpos monoclonais conjugados com radionuclídeos emissores α ou β-, ambos para terapia. O tratamento baseia-se na irradiação e destruição do tumor, preservando os órgãos normais quanto ao excesso de radiação. Radionuclídeos emissores β- como 90Y, 131I, 177Lu e 188Re, são úteis para o desenvolvimento de radiofármacos terapêuticos e, quando associados a AcM como o Anti-CD20 são importantes principalmente para o tratamento de Linfomas Não Hodgkins (LNH). 188Re (Eβ- = 2,12 MeV; Eγ= 155 keV; t1/2 = 16,9 h) é um radionuclídeo atrativo para RIT. O Centro de Radiofarmácia do IPEN possui um projeto que visa a produção do radiofármaco 188Re-Anti-CD20. Com isso,este estudo foi proposto para avaliar a eficácia desta técnica de marcação para tratamento em termos compartimentais e dosimétricos. O objetivo deste trabalho consistiu na compararação da marcação do AcM anti-CD20 com 188Re com a marcação do anticorpo com 90Y, 131I, 177Lu e 99mTc (pelas suas características químicas similares) e 211At, 213Bi, 223Ra e 225Ac. Através do estudo de técnicas de marcação relatadas em literatura, foi proposto um modelo compartimental para avaliação de sua farmacocinética e estudos dosimétricos, de alto interesse para a terapia. A revisão de dados publicados na literatura, possibilitou demonstrar diferentes procedimentos de marcação, rendimentos de marcação, tempo de reação, impurezas e estudos de biodistribuição. O resultado do estudo mostra uma cinética favorável para o 188Re, pelas suas características físicas e químicas frente aos demais radionuclídeos avaliados. O estudo compartimental proposto descreve o metabolismo do 188Re-anti-CD20 através de um modelo compartimental mamilar, que pela sua análise farmacocinética, realizada em comparação aos produtos marcados com emissores β-: 131I-antiCD20, 177Lu-anti-CD20, o emissor γ 99mTc-anti-CD20 e o emissor α 211At-Anti-CD20, apresentou uma constante de eliminação de aproximadamente 0,05 horas-1 no sangue do animal. A avaliação dosimétrica do 188Re-Anti-CD20 foi realizada através de duas metodologias: pelo método de Monte Carlo e pelo uso de uma fonte pontual β- através da Fórmula de Loevinger via programa Excel. Através da Fórmula de Loevinger fez-se a validação do método de Monte Carlo para a dosimetria do 188Re-Anti-CD20 e dos demais produtos. As doses e as taxas de doses obtidas pelos dois métodos foram avaliadas em comparação à dosimetria do 90Y-Anti-CD20, 131I-Anti-CD20 e do 177Lu-Anti-CD20, obtidas pela mesma metodologia. O estudo de dose foi realizado utilizando modelos matemáticos considerando um camundongo nude de 25g, simulando diferentes tamanhos de tumor e diferentes formas de distribuição do produto dentro do animal. De acordo com os resultados obtidos, pela energia de emissão β-, 188Re-Anti-CD20 apresenta maior deposição de energia para tumores volumosos em relação aos demais produtos avaliados. Em uma simulação com 100% do produto captado pelo tumor, 89% da dose total manteve-se absorvida pelo tumor, preservando a integridade de ógãos críticos como coração (2%), pulmões (5%), coluna (4%), fígado (0,014%) e rins (0,0007%). Em uma simulação onde há uma biodistribuição do produto no organismo do animal, 38% da dose total é absorvida pelo tumor e >3% é absorvida pela coluna. Nessa situação mais próxima da realidade, a extrapolação dos dados para um humano de 70kg, mostrou que a dose absorvida no tumor corresponde a cerca de 33%; na coluna 7% e o coração receberia uma dose de 35% do total. A análise compartimental e dosimétrica apresentada neste trabalho, realizada através do uso de um modelo animal para o 188Re-Anti-CD20 mostra que o produto desenvolvido e apresentado em literatura é candidato promissor para a RIT. / Tese (Doutorado em Tecnologia Nuclear) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP