Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2015-12-10T17:38:32Z No. of bitstreams: 0 / Made available in DSpace on 2015-12-10T17:38:32Z (GMT). No. of bitstreams: 0 / Neste trabalho foi desenvolvida uma nova metodologia de produção de iodo-125, que resultou na primeira produção deste radionuclídeo no Brasil. Cápsulas de alumínio foram projetadas, fabricadas e avaliadas para que suportassem condições de pressão, temperatura e fluxo de nêutrons no reator nuclear IEA-R1 do IPEN sem a ocorrência de liberação de material radioativo. Foram projetados, desenvolvidos e fabricados sistemas de carregamento, descarregamento e recuperação dos gases para a manipulação do gás xenônio e do iodo. Foi desenvolvido um novo método de lavagem da cápsula, para dissolução do iodo-125 adsorvido nas paredes, por meio de imersão em banho ultrassônico. Foram irradiadas três cápsulas no reator nuclear IEA-R1, por um período de aproximadamente 60 h contínuas, a um fluxo de nêutrons de 5,5 x 1013 n cm-2 s-1. Foi produzido um total de 13,53 GBq (365,73 mCi) de iodo-125, e o único contaminante encontrado foi o radionuclídeo iodo-126. Na análise radioquímica, pelo método de cromatografia em papel ascendente, o iodo-125 em solução de NaOH apresentou percentual de iodeto acima de 98%, superior à exigência da farmacopeia americana para soluções de iodo radioativo que é de 95%. Para a análise radionuclídica foi desenvolvida uma fonte planar, a base de resina epoxídica, para a contagem do iodo-125 em detector de germânio de alta pureza. A correlação entre o iodo-125 e o iodo-126 produzido apresentou valores entre 0,5 e 0,7% após um período de decaimento de 10 d, grau de pureza suficiente para a utilização em técnicas de radioimunoensaio. / Tese (Doutorado em Tecnologia Nuclear) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

No description available.

<p>A Monte Carlo simulation of the Neutron Wall detector system has been performed using Geant4, in order to define optimum conditions for the detection and identification of multiple neutrons. Emphasis was put on studying the scattering of neutrons between different detectors, which is the main source of the apparent increase of the number of detected neutrons. The simulation has been compared with experimental data. The quality of neutron gated γ-ray spectra was improved for both two- and three-neutron evaporation channels. The influence of small amounts of γ rays mis-interpreted as neutrons was investigated. It was found that such γ rays dramatically reduce the quality of neutron gated γ-ray spectra.</p><p>The interaction properties of fast neutrons in a closed-end coaxial and a planar high-purity germanium detector (HPGe) were studied. Digitised waveforms of HPGe preamplifier signals were recorded for time-of-flight separated neutrons and γ rays, emitted by a ²⁵²Cf source. The experimental waveforms from the detectors were compared to simulated pulse shapes. In the analysis, special emphasis was given to the detection of elastically scattered neutrons, which may be an important effect to take into account in future spectrometers based on γ-ray tracking. No differences between neutron and γ-ray induced pulse shapes were found in this work.</p><p>A Monte Carlo simulation of the interactions of fast neutrons in the future 4π γ-ray spectrometer AGATA was also performed, in order to study the influence of neutrons on γ-ray tracking. It was shown that although there is a large probability of detecting neutrons in AGATA, the neutrons decrease the photo-peak efficiency of AGATA by only about 1% for each neutron emitted in coincidence with γ rays. The peak-to-background ratios in γ-ray spectra are, however, reduced to a much larger extent. The possibility of using AGATA as a neutron detector system was also investigated.</p>

A Monte Carlo simulation of the Neutron Wall detector system has been performed using Geant4, in order to define optimum conditions for the detection and identification of multiple neutrons. Emphasis was put on studying the scattering of neutrons between different detectors, which is the main source of the apparent increase of the number of detected neutrons. The simulation has been compared with experimental data. The quality of neutron gated γ-ray spectra was improved for both two- and three-neutron evaporation channels. The influence of small amounts of γ rays mis-interpreted as neutrons was investigated. It was found that such γ rays dramatically reduce the quality of neutron gated γ-ray spectra. The interaction properties of fast neutrons in a closed-end coaxial and a planar high-purity germanium detector (HPGe) were studied. Digitised waveforms of HPGe preamplifier signals were recorded for time-of-flight separated neutrons and γ rays, emitted by a 252Cf source. The experimental waveforms from the detectors were compared to simulated pulse shapes. In the analysis, special emphasis was given to the detection of elastically scattered neutrons, which may be an important effect to take into account in future spectrometers based on γ-ray tracking. No differences between neutron and γ-ray induced pulse shapes were found in this work. A Monte Carlo simulation of the interactions of fast neutrons in the future 4π γ-ray spectrometer AGATA was also performed, in order to study the influence of neutrons on γ-ray tracking. It was shown that although there is a large probability of detecting neutrons in AGATA, the neutrons decrease the photo-peak efficiency of AGATA by only about 1% for each neutron emitted in coincidence with γ rays. The peak-to-background ratios in γ-ray spectra are, however, reduced to a much larger extent. The possibility of using AGATA as a neutron detector system was also investigated.

It is important to have a method of experimentally calculating fission product yields. Statistical calculations and simulations produce very large uncertainties. Experimental calculations, depending on the methods used, tend to produce lower uncertainties. This work set up a method to calculate fission product yields using gamma ray spectroscopy. In order to produce a method that was theoretically sound, a simulation was set up using OrigenArp to calculate theoretical concentrations of fission products from the irradiation of natural uranium. From these concentrations, the fission product yields were calculated to verify that they would agree with expected values. Moving forward in the work, the total flux at the point of irradiation, in the pneumatic transfer system, was calculated and determined to be 3.9070E+11 ± 6.9570E+10 n/cm^2/s at 100 kW. Once the flux was calculated, the method for calculating fission product yields was implemented and yields were calculated for 10 fission products. The yields calculated were in very good agreement (within 10.04%) with expected values taken from the ENDF-349 library. This method has strong potential in nuclear forensics as it can provide a means for developing a library of experimentally-determined fission product yields, as well as rapid post-nuclear detonation analysis. / text

摘要 i Abstract ii 誌謝 iv 表目錄 vii 圖目錄 1 一、 緒論 6 1-1前言 6 1-2研究動機與目的 7 1-3氫氧化鋁介紹 8 1-3-1氫氧化鋁結構 9 1-3-2氫氧化鋁之應用 10 1-4氧化鋁介紹 11 1-4-1氧化鋁晶型及結構 13 1-4-2氧化鋁之應用 16 二、 文獻回顧 17 2-1電漿定義及特徵 17 2-1-1非熱電漿之理論 21 2-1-2液相脈衝電漿之原理 24 2-1-3顆粒形成流程 28 2-1-4電漿法製備無機物粉末 30 2-2 製備α相氧化鋁粉末 41 2-2-1拜耳法 43 2-2-2溶膠凝膠法 48 2-2-3水熱法 50 2-2-4機械球磨法 56 2-2-5沉澱法 57 2-2-6燃燒法 59 三、 實驗方法與步驟 60 3-1實驗藥品與設備 60 3-2研究內容 63 3-3實驗流程與架構 65 3-4 本實驗設計之綠能特色 68 四、 結果與討論 69 4-1 氫氧化鋁之產量及反應機構 69 4-2氫氧化鋁之X-Ray繞射儀分析(X-Ray Diffractometer,XRD) 74 4-3氫氧化鋁之EDS(X-Ray energy dispersive spectrometer)分析 77 4-4氫氧化鋁之FE-SEM分析 78 4-5氫氧化鋁之粒徑分析 91 4-6氫氧化鋁之比表面積分析分析 94 4-7氧化鋁之鍛燒溫度探討 98 4-8氧化鋁之持溫時間探討 105 4-9氧化鋁添加硝酸銀之探討 111 4-10氧化鋁添加造孔劑之探討 118 五、 結論 124 六、 未來工作 126 參考文獻 127

Made available in DSpace on 2014-10-09T12:36:04Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:49Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Made available in DSpace on 2014-10-09T12:36:04Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:49Z (GMT). No. of bitstreams: 0 / O presente trabalho tem como objetivo a padronização de 68Ga, um emissor de pósitrons de meia-vida curta, usado em PET (Tomografia por Emissão de Pósitrons). A padronização do 68Ga foi realizada em um sistema de coincidência 4&pi;&beta;-&gamma;, que consiste de um detector proporcional em geometria 4&pi; a gás fluente acoplado a um detector de cristal semicondutor HPGe, para a detecção de raios gama. A aquisição de dados foi realizada por meio de um Sistema de Coincidência por Software (SCS), desenvolvido no Laboratório de Metrologia Nuclear (Laboratório de Metrologia Nuclear - LMN) no IPEN-CNEN / SP. Os resultados finais foram obtidos a partir de um ajuste de curva multiparamétrica aplicando-se uma metodologia que leva em consideração a matriz de covariância combinando os resultados experimentais com aqueles determinados pela simulação Monte Carlo. / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Submitted by Maria Eneide de Souza Araujo (mearaujo@ipen.br) on 2017-03-10T15:06:09Z No. of bitstreams: 1 23000.pdf: 2483857 bytes, checksum: ba54fa302ba8e46dabc056e73e8bd8ee (MD5) / Made available in DSpace on 2017-03-10T15:06:09Z (GMT). No. of bitstreams: 1 23000.pdf: 2483857 bytes, checksum: ba54fa302ba8e46dabc056e73e8bd8ee (MD5) / Rejeitos radioativos são gerados em todas as etapas do ciclo do combustível nuclear e em instituições que fazem uso de elementos radioativos. No Brasil, para que possam atender a legislação vigente, eles devem ser devidamente gerenciados e tratados. A caracterização é a etapa do gerenciamento de rejeitos radioativos que certifica e complementa as informações presentes no documento de identificação fornecido pelo gerador dos rejeitos radioativos. O objetivo desse trabalho foi desenvolver uma metodologia para caracterização de tambores de rejeitos radioativos. Neste trabalho foi utilizada a técnica de espectrometria gama associada ao método de Monte Carlo para obter e estabelecer uma relação entre as eficiências de contagens teóricas e experimentais para quatro tambores de calibração com densidades diferentes, preparados com nove tubos de PVC em seu interior. O detector de HPGe utilizado foi posicionado em três diferentes distâncias em relação a extremidade do tambor de calibração. A utilização do método de Monte Carlo mostrou-se adequado a metodologia proposta neste trabalho. / Dissertação (Mestrado em Tecnologia Nuclear) / IPEN/D / Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP

L’apparition de la segmentation électrique des détecteurs au GeHP et de l’électronique numérique a ouvert la voie à des applications prometteuses, telles que le tracking γ, l’imagerie γ ou la mesure bas bruit de fond, pour lesquelles une connaissance fine de la réponse du détecteur est un atout. L’IPHC a développé une table de scan utilisant un faisceau collimaté, qui sonde la réponse d’un détecteur dans tout son volume en fonction de la localisation de l’interaction. Elle est conçue pour utiliser une technique innovante de scan 3D, le Pulse Shape Comparison Scan, qui a été d’abord simulée afin de démontrer son efficacité. Un détecteur AGATA a été scanné de manière approfondie. Des scan 2D classiques ont permis, entre autres, de mettre en évidence des effets locaux de modification de la collection des charges, liés à la segmentation. Pour la première fois, une base de données 3D, complète, de formes d’impulsions fonction de la position d’interaction a été établie. Elle permettra notamment d’améliorer les performances du spectromètre AGATA. / Recent developments of electrical segmentation of HPGe detectors, coupled with digital electronics have led to promising applications such as γ-ray tracking, γ-ray imaging or low-background measurements which will benefit from a fine knowledge of the detector response. The IPHC has developed a new scanning table which uses a collimated γ-ray beam to investigate the detector response as a function of the location of the γ-ray interaction. It is designed to use the Pulse Shape Comparison Scan technique, which has been simulated in order to prove its efficiency. An AGATA detector has been thoroughly scanned. 2D classical scans brought out, for example, local charge collection modification effects such as charge sharing, due to the segmentation. For the first time, a 3D, complete pulse-shape database has been established. It will especially allow to improve the overall AGATA array performances.