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You searched for subject:(radiochemical laboratory). Showing records 1 – 2 of 2 total matches.

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1. Gauglitz, Érica. Estudo e levantamento de parâmetros para montagem de um laboratório de produção de fontes radioativas utilizadas na verificação de equipamentos.

Degree: Mestrado, Tecnologia Nuclear - Aplicações, 2010, University of São Paulo

Este trabalho apresenta o levantamento de parâmetros para implementação adequada e segura de pisos, portas, janelas, bancadas, capelas entre outros, de um laboratório radioquímico. A disposição de cada item segue orientações de guias, normas nacionais da Comissão Nacional de Energia Nuclear (CNEN) e internacional da Agencia Internacional de Energia Atômica (IAEA), com objetivo de garantir a proteção radiológica do trabalhador e do ambiente. A disposição adequada dos itens do laboratório radioquímico, garante a qualidade e segurança na produção de fontes radioativas seladas de 57Co 137Cs e 133Ba com atividades 185, 9.3 e 5.4 MBq respectivamente. Estas fontes são utilizadas na verificação de medidores de atividade, equipamento que todo Centro de Medicina Nuclear deve ter disponível segundo recomendações da norma CNEN-NN-3.05 Requisitos de Radioproteção e Segurança para Serviços de Medicina Nuclear para verificação da atividade de radiofármacos que serão administrados nos pacientes para fins de diagnóstico e terapia. Um medidor de atividade fora adquirido pelo laboratório de produção de fontes, com o qual foram realizados os testes de precisão, exatidão, reprodutibilidade e linearidade, que devem apresentar resultados dentro dos limites estabelecidos na norma CNEN-NN-3.05.

This paper presents a survey of parameters for the proper and safe flooring, doors, windows, fume hoods and others, in a radiochemical laboratory. The layout of each item follows guidelines and national standards of the National Commission of Nuclear Energy (CNEN) and the International Atomic Energy Agency (IAEA), aiming to ensure the radiological protection of workers and environment. The adequate items arrangement in the radiochemical laboratory ensures quality and safety in the production of 57Co 137Cs and 133Ba radioactive sealed sources, with activities 185, 9.3 and 5.4 MBq, respectively. These sources are used to verify meter activity equipment and should be available throughout the Nuclear Medicine Center, following the recommendations of CNEN-NN-3.05 standard \"Requirements for Radiation Protection and Safety Services for Nuclear Medicine\", to verify the activity of radiopharmaceuticals that are administered in patients, for diagnosis and therapy.

Advisors/Committee Members: Rostelato, Maria Elisa Chuery Martins.

Subjects/Keywords: laboratório radioquímico; measuring activity and sealed radioactive sources; medidor de atividade e fontes radioativas seladas; radiochemical laboratory

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Gauglitz, . (2010). Estudo e levantamento de parâmetros para montagem de um laboratório de produção de fontes radioativas utilizadas na verificação de equipamentos. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85131/tde-08082011-143953/ ;

Chicago Manual of Style (16th Edition):

Gauglitz, Érica. “Estudo e levantamento de parâmetros para montagem de um laboratório de produção de fontes radioativas utilizadas na verificação de equipamentos.” 2010. Masters Thesis, University of São Paulo. Accessed October 14, 2019. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-08082011-143953/ ;.

MLA Handbook (7th Edition):

Gauglitz, Érica. “Estudo e levantamento de parâmetros para montagem de um laboratório de produção de fontes radioativas utilizadas na verificação de equipamentos.” 2010. Web. 14 Oct 2019.

Vancouver:

Gauglitz . Estudo e levantamento de parâmetros para montagem de um laboratório de produção de fontes radioativas utilizadas na verificação de equipamentos. [Internet] [Masters thesis]. University of São Paulo; 2010. [cited 2019 Oct 14]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85131/tde-08082011-143953/ ;.

Council of Science Editors:

Gauglitz . Estudo e levantamento de parâmetros para montagem de um laboratório de produção de fontes radioativas utilizadas na verificação de equipamentos. [Masters Thesis]. University of São Paulo; 2010. Available from: http://www.teses.usp.br/teses/disponiveis/85/85131/tde-08082011-143953/ ;


Texas A&M University

2. Sternat, Matthew Ryan 1982-. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel.

Degree: 2012, Texas A&M University

Pre-detonation technical nuclear forensics techniques for research reactor spent fuel were developed in a collaborative project with Savannah River National Lab ratory. An inverse analysis method was employed to reconstruct reactor parameters from a spent fuel sample using results from a radiochemical analysis. In the inverse analysis, a reactor physics code is used as a forward model. Verification and validation of different reactor physics codes was performed for usage in the inverse analysis. The verification and validation process consisted of two parts. The first is a variance analysis of Monte Carlo reactor physics burnup simulation results. The codes used in this work are MONTEBURNS and MCNPX/CINDER. Both utilize Monte Carlo transport calculations for reaction rate and flux results. Neither code has a variance analysis that will propagate through depletion steps, so a method to quantify and understand the variance propagation through these depletion calculations was developed. The second verification and validation process consisted of comparing reactor physics code output isotopic compositions to radiochemical analysis results. A sample from an Oak Ridge Research Reactor spent fuel assembly was acquired through a drilling process. This sample was then dissolved in nitric acid and diluted in three different quantities, creating three separate samples. A radiochemical analysis was completed and the results were compared to simulation outputs at different levels ofdetail. After establishing a forward model, an inverse analysis was developed to re-construct the burnup, initial uranium isotopic compositions, and cooling time of a research reactor spent fuel sample. A convergence acceleration technique was used that consisted of an analytical calculation to predict burnup, initial 235U, and 236U enrichments. The analytic calculation results may also be used stand alone or in a database search algorithm. In this work, a reactor physics code is used as a for- ward model with the analytic results as initial conditions in a numerical optimization algorithm. In the numerical analysis, the burnup and initial uranium isotopic com- positions are reconstructed until the iterative spent fuel characteristics converge with the measured data. Upon convergence of the sample?s burnup and initial uranium isotopic composition, the cooling time can be reconstructed. To reconstruct cooling time, the standard decay equation is inverted and solved for time. Two methods were developed. One method uses the converged burnup and initial uranium isotopic compositions along in a reactor depletion simulation. The second method uses an isotopic signature that does not decay out of its mass bin and has a simple production chain. An example would be 137Cs which decays into the stable 137Ba. Similar results are achieved with both methods, but extended shutdown time or time away from power results in over prediction of the cooling time. The over prediction of cooling time and comparison of different burnup reconstruction isotope… Advisors/Committee Members: Charlton, William S (advisor), Boyle, David R (committee member), Adams, Marvin L (committee member), Folden, Charles M (committee member).

Subjects/Keywords: Attribution; Spent Fuel; Research Reactor; Savannah River National Laboratory; Radiochemical Analysis; Inverse Reactor Physics; Inverse Problems; Nuclear Forensics

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Sternat, M. R. 1. (2012). Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/148202

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Sternat, Matthew Ryan 1982-. “Development of Technical Nuclear Forensics for Spent Research Reactor Fuel.” 2012. Thesis, Texas A&M University. Accessed October 14, 2019. http://hdl.handle.net/1969.1/148202.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Sternat, Matthew Ryan 1982-. “Development of Technical Nuclear Forensics for Spent Research Reactor Fuel.” 2012. Web. 14 Oct 2019.

Vancouver:

Sternat MR1. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Oct 14]. Available from: http://hdl.handle.net/1969.1/148202.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Sternat MR1. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/148202

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

.