Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2015-12-22T09:13:03Z No. of bitstreams: 0 / Made available in DSpace on 2015-12-22T09:13:03Z (GMT). No. of bitstreams: 0 / A aceitação de rejeitos radioativos em um repositório final depende, entre outras coisas, do conhecimento do inventário radioisotópico presente neles. Para obter essa informação, é necessário fazer a caracterização primária dos rejeitos de modo que a composição seja conhecida e oriente os passos seguintes da gestão. Os filtros cartucho que são utilizados no sistema de retratamento de água do reator de pesquisa IEA-R1 é um desses rejeitos. O IEA-R1 é um reator de pesquisa do tipo piscina, operando entre 2 e 5 MW, que utiliza a água como líquido de arrefecimento, moderador e blindagem biológica Além do seu uso em pesquisa, também é utilizado para produzir radioisótopos e irradiar amostras. Ele está localizado no Instituto de Pesquisas Energéticas e Nuclear, no campus da Universidade de São Paulo. Os filtros cartucho são utilizados para reter o material particulado em suspensão presente na água. Quando os filtros ficam saturados e são incapazes de manter o fluxo dentro dos limites estabelecidos, eles são substituídos e descartados como rejeito radioativo. Após um período de espera para o decaimento da atividade, são enviados para Gerência de Rejeitos Radioativos (GRR). O objetivo deste trabalho é apresentar os estudos realizados para determinar a atividade dos emissores gama presentes nos filtros cartucho. As atividades foram calculadas utilizando as taxas de dose medidas com detectores portáteis, as relações entre as taxas de emissão de fótons avaliadas por espectrometria gama, e o método de Point Kernel, que correlaciona a atividade de uma fonte com as taxas de dose a várias distâncias. O método descrito pode ser utilizado para determinar de modo rotineiro o inventário radioisotópico destes filtros, dispensando análises radioquímicas destrutivas, e a necessidade de calibração da geometria de medição. / Dissertação (Mestrado em Tecnologia Nuclear) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

The purpose of the work described in this thesis was to explore the use of fractional crystallization as a technology that can be used to separate medium-curie waste from the Hanford Site tank farms into a high-curie waste stream, which can be sent to a Waste Treatment and Immobilization Plant (WTP), and a low-curie waste stream, which can be sent to Bulk Vitrification. The successful semi-batch crystallization of sodium salts from two single shell tank simulant solutions (SST Early Feed, SST Late Feed) demonstrated that the recovered crystalline product met the purity requirement for exclusion of cesium, sodium recovery in the crystalline product and the requirement on the sulfate-to-sodium molar ratio in the stream to be diverted to the WTP. The experimental apparatus, procedures and results obtained in this thesis on scaled-down experiments of SST Early and Late Feed simulated solutions were adapted and reproduced under hot-cell with actual wastes by our partners at Hanford. To prepare the application of the pretreatment process to pilot scale process, several varation to the feed solutions were investigated including the presence of carboxylates and amines organics compounds and solids particles. Results of the study showed that 4 organics species presented complications to the process (NTA, HEDTA, EDTA and sodium citrate) while the other species (Formate, acetate, glycolate and IDA) and solids particles did not in the conditions of the stored wastes. In this thesis, the kinetics of the crystalline species formed at the condition of the early feed certification run (66 °C and 25 g/h evaporation) were determined along with the effect of the operating temperature and evaporation rate on these kinetics. On one hand, the study of evaporation rate values ranging from 25g/h to 75g/h showed that an increase in evaporation rate increased the specific nucleation while decreasing the specific growth rate. On the other hand, experiments on operating temperature ranging from 35 °C to 75 °C displayed that the nucleation rate of all species increased with temperature at the exception of sodium carbonate monohydrate and burkeite crystals, and that the growth rate of all species increased with temperature at the exception of sodium nitrate. Furthermore, sulfate based crystals such as trisodium fluoride sulfate were only roduced at 45 °C and 75 °C. A simple steady state MSMPR population balance model was developed expressing the total population density function as the sum of the specific population density functions. The specific semi-batch crystallization kinetics were implemented in this model.

Call number: LD2668 .T4 1985 R33 / Master of Science

First-principles calculations such as density functional theory (DFT) employ numerical approaches to solve the Schrodinger equation of a system. Standard functionals employed to determine the cohesive system energy, specifically the local density and generalized gradient approximations (LDA and GGA), underestimate the correlation of 5f electrons to their ions in AO₂ systems (A=U/Pu/Np). The standard correction, the "Hubbard +U," causes the multidimensional energy surface to develop a large number of local minima which do not correspond to the ground state (global minimum). Because all useful energy values derived from DFT calculations depend on small differences between relatively large cohesive energies, comparing systems wherein one or more of the samples are not in the ground state has the potential to introduce large errors. This work presents an analysis of the fundamental issues of metastable states in both pure and binary AO₂ systems, investigates novel methods of handling them, and describes why current literature approaches which appear to work well for the pure compounds are not well-suited for systems containing multiple actinide species.

Thesis (M.S.)--Mississippi State University. Department of Chemical Engineering. / Title from title screen. Includes bibliographical references.

Experiments were performed at the Nuclear Engineering Teaching Laboratory (NETL) in 2005 and 2006 in which a 20 MeV linear electron accelerator operating as a photoneutron source was coupled to the TRIGA (Training, Research, Isotope production, General Atomics) Mark II research reactor at the University of Texas at Austin (UT) to simulate the operation and characteristics of a full-scale accelerator driven subcritical system (ADSS). The experimental program provided a relatively low-cost substitute for the higher power and complexity of internationally proposed systems utilizing proton accelerators and spallation neutron sources for an advanced ADSS that may be used for the burning of high-level radioactive waste. Various instrumentation methods that permitted ADSS neutron flux monitoring in high gamma radiation fields were successfully explored and the data was used to evaluate the Stochastic Pulsed Feynman method for reactivity monitoring. / text

Thesis (Ph. D.)--Auburn University, 2007. / Abstract. Vita. Includes bibliographical references.

Thesis (M.S.)--Mississippi State University. Dave C. Swalm School of Chemical Engineering. / Title from title screen. Includes bibliographical references.

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Made available in DSpace on 2014-10-09T12:26:22Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:04:32Z (GMT). No. of bitstreams: 0 / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP