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Rojo, A.M.; Gómez Parada, I.; Gossio, S.; Puerta Yepes, N.; Saavedra, A.D.; Segato, A.D., E-mail: arojo@arn.gob.ar
Technical Memory 2011. Nuclear Regulatory Authority2011
Technical Memory 2011. Nuclear Regulatory Authority2011
AbstractAbstract
[en] Dose assessment in case of internal exposure involves the estimation of committed effective dose based on the interpretation of bioassay measurement, and the assumptions of hypotheses on the characteristics of the radioactive material and the time pattern and the pathway of intake. In the case of workers exposed in nuclear fuel facilities, the normal uranium excretion from the diet is an additional difficulty in the process of assessing internal exposure. The aim of this paper is to present the main topics discussion and the conclusions of the workshop, held in the frame of the missions of the Autoridad Regulatoria Nuclear. All the personnel involved in the control of internal exposure in nuclear fuel cycle was invited to participate in the workshop to discuss about individual monitoring criteria and the available tools for assessing committed effective dose in the workers of their facilities. The lectures were presented jointly by the Nuclear Fuel Cycle Facilities Control and the Dosimetric and Radiobiological Assessment departments. It was hold at the Ezeiza Atomic Center from 23th to 24th November 2010 based on the Advanced Course on Internal Dosimetry organized on 2009 and focusing specific uranium compound internal dosimetry. A representative of each facility was invited to present the monitoring program implemented for controlling the internal exposure. It was an opportunity to discuss criteria and to share experiences on this field in the frame of the ICRP, HPA and ISO publications. The different monitoring program criteria could be analyzed and so contributing to the improvement of radiological protection. Finally, it was agreed to hold periodical meetings to assure the update on uranium measurement techniques and the handling of monitoring data for committed effective dose assessment. (authors)
[es]
El cálculo de la dosis efectiva, en los casos de exposición interna de trabajadores, requiere de la evaluación de la actividad incorporada a partir del análisis de datos de medición utilizando modelos biocinéticos y dosimétricos. En el caso de la exposición a uranio existe una dificultad adicional en el análisis de los datos de monitoreo debido a la excreción de uranio natural proveniente de la dieta. El objetivo de este trabajo es presentar los contenidos y el balance de estas Jornadas realizadas en el marco de las funciones de control y asesoramiento por parte de la Autoridad Regulatoria Nuclear a responsables de áreas controladas. Dada la importancia de un abordaje específico en estos temas, se convocó a todos los involucrados en el control de la exposición interna de los trabajadores del ciclo de combustible a participar para discutir aspectos de interés sobre los planes de monitoreo y las herramientas de cálculo disponibles. Esta actividad conjunta entre los Departamentos Control de Instalaciones del Ciclo de Combustible y Evaluaciones Dosimétricas y Radiobiológicas se desarrolló entre el 23 y el 24 de noviembre de 2010 y se realizó tomando como base el curso de Métodos Avanzados de Dosimetría Interna organizado en agosto de 2009 y enfocando las particularidades de la dosimetría interna para uranio. (autores)Original Title
Jornada de actualización en dosimetría interna para el ciclo de combustible
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Source
Autoridad Regulatoria Nuclear, Buenos Aires (Argentina); 188 p; 2011; p. 141-147; 38. Annual Meeting of the Argentine Association of Nuclear Technology; Buenos Aires (Argentina); 14-18 Nov 2011; Also available on-line at http://www.arn.gob.ar/images/stories/informes_y_documentos/memoria_tecnica/MT_2011/mt17_11_rojo.pdf; 8 refs.,1 fig.
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Miscellaneous
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Conference; Progress Report
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