Simplified semi-analytical model for mass transport simulation in unsaturated zone
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2001
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REGIONAL CONGRESS ON RADIATION PROTECTION AND SAFETY, 5th, REGIONAL IRPA CONGRESS
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Resumo
This paper describes a simple model to determine the flux of radionuclides released
from a concrete vault repository and its implementation through the development of a
computer program. The radionuclide leach rate from waste is calculated using a model
based on simple first order kinetics and the transport through porous media bellow the
waste is determined using a semi-analytical solution of the mass transport equation.
Results obtained in the AIEA intercomparison program are also related in this
communication.
Como referenciar
VIEIRA de SA, B.L.; HIROMOTO, G. Simplified semi-analytical model for mass transport simulation in unsaturated zone. In: REGIONAL CONGRESS ON RADIATION PROTECTION AND SAFETY, 5th, REGIONAL IRPA CONGRESS, Apr. 29 - May 4, 2001, Recife, PE. Proceedings... Disponível em: http://repositorio.ipen.br/handle/123456789/15238. Acesso em: 30 Dec 2025.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.