Modelling the transport of radionuclides released in the Ilha Grande bay (BRAZIL) after a LBLOCA in the primary system of A PWR

• Autor(a) principal: Aguiar, André Silva de
• Data de Publicação: 2011
• Outros Autores: Simões Filho, Francisco Fernando Lamego, Soares, Abner Duarte, Lapa, Celso Marcelo Franklin, Instituto de Engenharia Nuclear, Instituto Nacional de Ciência e Tecnologia de Reatores Nucleares Inovadores
• Tipo de documento: Artigo de conferência
• Idioma: eng
• Título da fonte: Repositório Institucional do IEN
• Texto Completo: http://carpedien.ien.gov.br:8080/handle/ien/2429
• topic: INAC 2011; Nuclear reactor; Radionuclide; Radiological impact

It was postulated, in the cooling system of the core, a LOCA, where 431 m³ of soda almost instantaneously was lost. This inventory contained 1.87x1010 Bq/m³ of tritium, 2.22x107 Bq/m³ of cobalt,3.48x108 Bq/m³ of cesium and 3.44x1010 Bq/m³ of iodine and was released in liquid form near the Itaorna cove, Angra dos Reis – RJ. Applying the model in the proposed scenario (Angra 1 and 2 in operation and Angra 3 progressively reducing the capture and discharge after the accident), the simulated dilution of the specific activity of radionuclide spots, reached values much lower than report levels for seawater (1,1x106 Bq/m³, 1,11x104 Bq/m³ and 1,85x103 Bq/m³) after 22 hours, respectively for ³H, 60Co, 131I and 137Cs. From the standpoint of public exposure to radionuclide dispersion, the results of activity concentration obtained by the model suggest that the observed radiological impact is negligible. Based on these findings, we conclude that there would be no radiological impact related to a further release of controlled effluent discharges into Itaorna cove.