Villavicencio, Facundo L. (2019) Calibración de equipos de centelleo líquido en H-3 y C-14 con fines de protección radiológica en personal radiológicamente expuesto en centrales nucleares de agua pesada. Asignación de dosis de ambos radionucleídos a los agentes evaluados. / Calibration of H-3 and C-14 liquid scintillation equipment for radiation protection purposes on radiologically exposed personnel in heavy water nuclear power plants. Dose allocation of both radionuclides to the agents evaluated. Trabajo Final (CEATEN), Universidad Nacional de Cuyo, Instituto Balseiro.
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Resumen en español
La exposición a radiación interna en reactores de agua pesada presurizada (PHWR) representa aproximadamente el 20 ~ 40% de exposición total a la radiación; la mayor exposición a la radiación interna se atribuye al tritio. El carbono 14 no es un nucleído dominante en la exposición a la radiación de los trabajadores, pero es uno potencial para ser necesariamente monitoreado. El carbono 14 es un emisor beta de baja energía y pasa relativamente fácil al cuerpo de los trabajadores por inhalación, pues su forma química dominante es el dióxido de carbono radiactivo (14CO2). La mayor parte del carbono inhalado es rápidamente exhalada del organismo del trabajador, pero una pequeña cantidad queda dentro y es excretada vía orina. El objetivo de este trabajo es, previa calibración de un equipo de centelleo líquido, desarrollar un método para medir en forma simultánea el contenido de Tritio y el eventual de C-14 a cada muestra de orina que realiza un trabajador del Complejo Nuclear Atucha, y establecer un protocolo especial para lograr un conteo dual de ambos radionucleídos con mayor exactitud en orina de una persona en caso de ser necesario o para corroborar aquellas mediciones en la cuales se sospeche presencia del mismo. A partir de las mediciones de cuentas, se asignará la dosis interna a cada trabajador.
Resumen en inglés
Internal radiation exposure at PHWRs accounts for approximately 20 ~ 40% of total radiation exposure; most internal radiation exposure is attributed to tritium. Carbon-14 is not a dominant nuclide in the radiation exposure of workers, but it is one potential nuclide to be necessarily monitored. Carbon-14 is a low energy beta emitter and passes relatively easily into the body of workers by inhalation because its dominant chemical form is radioactive carbon dioxide (14CO2). Most inhaled carbon-14 is rapidly exhaled from the worker’s body, but a small amount of carbon-14 remains inside the body and is excreted by urine. The objective of this work is, prior calibration of a liquid scintillation device, to develop a method to simultaneously measure the content of Tritium and C-14 to every urine sample submitted by a worker at Atucha Nuclear Power Plant, and establish a special protocol to achieve the dual counting of both radionuclides with greater accuracy in a person's urine if necessary or to corroborate those measurements in which the presence of those nucleides is suspected. From the counting results, the internal dose will be assigned to each worker.
| Tipo de objeto: | Tesis (Trabajo Final (CEATEN)) |
|---|---|
| Palabras Clave: | Titrium; Tritio; Carbon 14; Carbono 14; [Liquid scintillation; Centelleo líquido; Dual counting; Conteo dual; Internal dose assignment; Asignación de dosis interna] |
| Referencias: | [1] Tritium accounting for PHWR plants. Nair, P.S. (Operating Plants Safety Division, Atomic Energy Regulatory Board, Mumbai (India)); Duraisamy, S. (Operating Plants Safety Division, Atomic Energy Regulatory Board, Mumbai (India)). [2] Development of the Dual Counting and Internal Dose Assessment Method for Carbon-14 at Nuclear Power Plants. HEE GEUN KIM, TAE YOUNG KONG, SANG JUN HAN and GOUNG JIN LEE. JOURNAL OF RADIATION PROTECTION, VOL.34 NO.2 JUNE 2009. [3] Whillans DW, Thind KS. Internal Dosimetry for Short- Range Emitters. In: Health Physics Society 1995 Summer School (Radiation Protection at Nuclear Reactors). Medical Physics Publishing Madison, Wisconsin. 1995. [4] Korea Electric Power Corporation. Final Safety Analysis Report for Wolsong Unit 2,3,4 Nuclear Power Plants, Rev. 31. 2000. [5] International Atomic Energy Agency, Methods for Assessing Occupational Radiation Doses Due to Intakes of Radionuclides, Safety Report Series No. 37, (2004). [6] Korea Hydro and Nuclear Power Co., Standard Procedure in Nuclear Power Plants: Measurement and Assessment of Internal Dose, Radiation-06, (2008). [7] International Commission on Radiological Protection, Individual Monitoring for Internal Exposure of Workers, Replacement of ICRP Publication 54, ICRP Publication 78, Annals of the ICRP, Pergamon Press, Oxford, UK, (1997). [8] International Atomic Energy Agency, Methods for Assessing Occupational Radiation Doses Due to Intakes of Radionuclides, Safety Report Series No. 37, (2004). [9] Kim HG, Lee HS, Ha GH. An Analysis of Carbon-14 Metabolism for Internal Dosimetry at CANDU Nuclear Power Plants. Journal of Radiation Protection 2003 Sep.;28(3):207-213. [10] Korea Hydro & Nuclear Power Corporation. Development on the C-14 Internal Dosimetry for Nuclear Power Plant Workers. 2008. [11] Korea Electric Power Research Institute. Technical Report of the Analysis Method of Tritium and C-14 in Urine Samples of Radiation Workers. Technical Memo. 2007. [12] Atomic Energy Control Board. Bioassay Technical Reference Criteria Radioactive Carbon - Report of the AECB Working Group on Internal Dosimetry. 1994. [13] Whillans DW. Structure of a Physiologically Based Biokinetic Model for Use in 14C and Organically Bound Tritium Dosimetry. Radiation Protection Dosimetry 2003:105(1-4). |
| Materias: | Medicina > Protección radiológica del paciente |
| Divisiones: | Central Nuclear Atucha II |
| Código ID: | 1126 |
| Depositado Por: | Tamara Cárcamo |
| Depositado En: | 07 Mar 2023 10:44 |
| Última Modificación: | 07 Mar 2023 10:44 |
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