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Master's Dissertation
DOI
10.11606/D.85.2015.tde-18082015-092143
Document
Author
Full name
Débora Harumi Suzuki Hara
E-mail
Institute/School/College
Knowledge Area
Date of Defense
Published
São Paulo, 2015
Supervisor
Committee
Rossi, Jesualdo Luiz (President)
Mucsi, Cristiano Stefano
Sene, Frank Ferrer
Title in Portuguese
Seleção de materiais para embalado de transporte de Mo-99
Keywords in Portuguese
blindagem
embalado
seleção de materiais
Abstract in Portuguese
O transporte de materiais radioativos deve ser realizado em embalados capazes de suportar tanto condições normais, quanto acidentais de transporte. O objetivo deste trabalho foi a seleção de materiais que possam viabilizar a fabricação de um embalado para o transporte de substâncias que sejam fontes de alta radioatividade, em especial o Mo-99, cujo produto do decaimento radioativo é o Tc-99m, utilizado para fins diagnósticos na medicina nuclear. Para tanto, foi realizada a seleção dos possíveis materiais que podem ser utilizados para a fabricação de um embalado, com o auxílio do programa CES EduPack e a metodologia desenvolvida por Ashby. O programa ESTAR foi utilizado para verificar a ocorrência de radiação de freamento e o programa XCOM para o cálculo do coeficiente de atenuação da radiação gama de alguns dos materiais selecionados para compor a blindagem do embalado. Posteriormente, a espessura necessária para a blindagem da radiação foi calculada. A partir dos resultados obtidos, os materiais selecionados como candidatos potenciais para a fabricação da blindagem foram as ligas de tungstênio. Com relação à parte do embalado que oferece isolamento térmico e proteção ao impacto, destacam-se as madeiras, os aglomerados e os compensados. No que concerne ao revestimento interno e externo, os materiais selecionados se concentram nos aços.
Title in English
Material selection for a transportation package of Mo-99
Keywords in English
materials selection
package
shielding
Abstract in English
The transport of radioactive materials must be done in packages able to withstand both normal and accidental conditions of transport. The aim of this work was the material selection that can enable the manufacture of a package for the transport of substances which are of high radioactivity sources, especially Mo-99, whose radioactive decay product is Tc-99m, used for diagnosis purposes in nuclear medicine. For this, the selection of possible materials that can be used for the manufacture of the main parts of the package was performed with the aid of CES Edupack program and the methodology developed by Ashby. The ESTAR program was used to check occurrence of Bremsstrahlung and the XCOM program was used to calculate the attenuation coefficient of gamma radiation from some of the selected materials for the shield. After, the thickness needed for the radiation shielding was calculated. From the results, the materials selected as potential candidates for the manufacture of the shielding was the tungsten alloys. Related to the thermal insulation and the impact protection, woods, plywoods and particleboards stand out. With regard to internal and external recipients, the selected materials focus on steels.
 
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Publishing Date
2015-08-18
 
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