De acordo com a Comissão Nacional de Energia Nuclear (CNEN), a avaliação de impacto radiológico ambiental resultante da liberação de radionuclídeos para o meio ambiente, devido à operação normal de instalações nucleares, para propósito de proteção do público, é feita considerando o conceito de grupo crítico. Contudo, em 2006, a International Commission on Radiological Protection (ICRP), para o mesmo propósito, propôs a adoção do conceito de indivíduo representativo. Uma vez que, em algum momento, o Brasil possa adotar esse novo conceito, no presente trabalho são avaliadas as alterações, em termos de procedimentos de cálculo e dos consequentes resultados, decorrentes da aplicação da metodologia de indivíduo representativo em comparação com a metodologia de grupo crítico atualmente utilizada para o controle regulatório das instalações nucleares brasileiras. Como referência, utilizou-se as potenciais liberações de radionuclídeos previstas para a operação normal da Unidade de Produção de Hexafluoreto de Urânio (USEXA), localizada no Centro Experimental Aramar (CEA). De forma específica, os objetivos são: efetuar a avaliação de impacto radiológico ambiental para o CEA, utilizando as duas metodologias recomendadas (determinística e probabilística) para o indivíduo representativo, conforme descritas pela ICRP (2006); efetuar a comparação dos resultados obtidos com essas metodologias com os obtidos com a metodologia utilizada para o grupo crítico; e efetuar uma análise crítica da necessidade e da disponibilidade de dados para a aplicação dessas metodologias, bem como das suas consequências para o controle operacional do CEA. Com base nos resultados obtidos, destaca-se que a utilização da metodologia de cálculo de grupo crítico continua sendo uma maneira simples e eficiente para a avaliação de impacto radiológico ambiental, quando comparada à utilização da metodologia de indivíduo representativo, o que torna o estabelecimento de programas de monitoramento e, consequentemente, o controle radiológico ambiental, mais simples e objetivos. / According to the National Commission for Nuclear Energy (CNEN), the assessment of environmental radiological impact from the release of radionuclides to the environment due to normal operation of nuclear facilities, for protecting the public, considers the concept of critical group. In 2006, the International Commission on Radiological Protection (ICRP), for the same purpose, proposed the adoption of the concept of representative person. Once, at some point, this new concept probably will be adopted in Brazil, in this study the changes in terms of procedures for calculating and consequent results arising from the application of the representative person methodology are evaluated and compared to the critical group methodology currently used for regulatory control of Brazilian nuclear facilities. As a reference, it was used the predicted potential releases of radionuclides resulting from the normal operation of the Uranium Hexafluoride Production Plant (USEXA), located at Centro Experimental Aramar (CEA). Specifically, the objectives are: to carry out the environmental radiological impact for CEA, using the two recommended methods (deterministic and probabilistic) for the representative person, as described by the ICRP (2006); to make the comparison of results obtained with these methods with those obtained with the methodology used for the critical group; and, make a critical analysis of the need and the availability of data for the application of these methodologies, as well as its consequences for the operational control of CEA. Based on the results obtained, it is emphasized that the use of the methodology for calculating critical group remains a simple and efficient way to evaluate radiological environmental impact when compared to the use of the representative person methodology, which makes the establishment of monitoring programs, and therefore the environmental radiological control, simpler and objectives.

De acordo com a Comissão Nacional de Energia Nuclear (CNEN), a avaliação de impacto radiológico ambiental resultante da liberação de radionuclídeos para o meio ambiente, devido à operação normal de instalações nucleares, para propósito de proteção do público, é feita considerando o conceito de grupo crítico. Contudo, em 2006, a International Commission on Radiological Protection (ICRP), para o mesmo propósito, propôs a adoção do conceito de indivíduo representativo. Uma vez que, em algum momento, o Brasil possa adotar esse novo conceito, no presente trabalho são avaliadas as alterações, em termos de procedimentos de cálculo e dos consequentes resultados, decorrentes da aplicação da metodologia de indivíduo representativo em comparação com a metodologia de grupo crítico atualmente utilizada para o controle regulatório das instalações nucleares brasileiras. Como referência, utilizou-se as potenciais liberações de radionuclídeos previstas para a operação normal da Unidade de Produção de Hexafluoreto de Urânio (USEXA), localizada no Centro Experimental Aramar (CEA). De forma específica, os objetivos são: efetuar a avaliação de impacto radiológico ambiental para o CEA, utilizando as duas metodologias recomendadas (determinística e probabilística) para o indivíduo representativo, conforme descritas pela ICRP (2006); efetuar a comparação dos resultados obtidos com essas metodologias com os obtidos com a metodologia utilizada para o grupo crítico; e efetuar uma análise crítica da necessidade e da disponibilidade de dados para a aplicação dessas metodologias, bem como das suas consequências para o controle operacional do CEA. Com base nos resultados obtidos, destaca-se que a utilização da metodologia de cálculo de grupo crítico continua sendo uma maneira simples e eficiente para a avaliação de impacto radiológico ambiental, quando comparada à utilização da metodologia de indivíduo representativo, o que torna o estabelecimento de programas de monitoramento e, consequentemente, o controle radiológico ambiental, mais simples e objetivos. / According to the National Commission for Nuclear Energy (CNEN), the assessment of environmental radiological impact from the release of radionuclides to the environment due to normal operation of nuclear facilities, for protecting the public, considers the concept of critical group. In 2006, the International Commission on Radiological Protection (ICRP), for the same purpose, proposed the adoption of the concept of representative person. Once, at some point, this new concept probably will be adopted in Brazil, in this study the changes in terms of procedures for calculating and consequent results arising from the application of the representative person methodology are evaluated and compared to the critical group methodology currently used for regulatory control of Brazilian nuclear facilities. As a reference, it was used the predicted potential releases of radionuclides resulting from the normal operation of the Uranium Hexafluoride Production Plant (USEXA), located at Centro Experimental Aramar (CEA). Specifically, the objectives are: to carry out the environmental radiological impact for CEA, using the two recommended methods (deterministic and probabilistic) for the representative person, as described by the ICRP (2006); to make the comparison of results obtained with these methods with those obtained with the methodology used for the critical group; and, make a critical analysis of the need and the availability of data for the application of these methodologies, as well as its consequences for the operational control of CEA. Based on the results obtained, it is emphasized that the use of the methodology for calculating critical group remains a simple and efficient way to evaluate radiological environmental impact when compared to the use of the representative person methodology, which makes the establishment of monitoring programs, and therefore the environmental radiological control, simpler and objectives.

This thesis deals with the influence of the discharges of the Dukovany Nuclear Power Plant ("Dukovany NPP") and the assessment of impacts on the population and the vicinity of the power plant. The thesis summarizes the issues of tritium 3H discharges into waterways and partially deals with the 14C discharges. Attention is paid especially to the radioisotope of hydrogen 3H, due to its chemical and physical form and its presence in the cooling medium (light water) used by that type of nuclear power reactor. The thesis also contains a description of the current state of the Dukovany NPP, especially the existing discharges of the radioactive substances to the surroundings of the nuclear power plant, both to the air and into the waterway. Also was discussed the issue of the new planned blocks of the Dukovany NPP and impacts of the projected discharges on the population during the simultaneous operation of the existing blocks and the planned blocks, again in relation to the 3H discharged into the waterway. The application ESTE AI was used for the determination of individual groups of inhabitants who are most exposed to the radioactive discharges (also called representative person). Based on the current discharges of the Dukovany NPP and the planned blocks discharges were determined the annual effective doses for a representative person. The doses were compared with the legislation on the conditions for the peaceful use of nuclear energy requirements and then with the water management legislation. In order to avoid exceeding these limits were set up recommendations how to dispose of radioactive substances optimally. The thesis answer to the research question: What impacts on the population will have discharges of the Dukovany NPP after the construction of a new nuclear source, especially in relation to the discharges of the 3H into the waterway and which measures will must be applied on the optimization of the inhabitants doses.