Calibration of gamma cameras for the Evaluation of Accidental Intakes of high-energy photon emitting Radionuclides by humans based on Urine Samples
DOI:
https://doi.org/10.15392/bjrs.v6i2A.783Palabras clave:
Internal dosimetry, in vitro measurements, bioassay, gamma camera, emergency, radiological accidentsResumen
The prompt response to emergency situations involving suspicion of intakes of radionuclides requires the use of simple and rapid methods of internal monitoring of the exposed individuals. The use of gamma cameras to estimate intakes and committed doses was investigated by the Centers for Disease Control and Preventions (CDC) of the USA in 2010.The present study aims to develop a calibration protocol for gamma cameras to be applied on internal monitoring based on urine samples to evaluate the incorporation of high-energy photon emitting radionuclides in emergency situations. A gamma camera available in a public hospital located in the city of Rio de Janeiro was calibrated using a standard liquid source of 152Eu supplied by the LNMRI of the IRD. “Efficiency vs Energy” curves at 2 and 10 cm were obtained. Calibration factors, Minimum Detectable Activities and Minimum Detectable Effective Doses of the gamma camera were calculated for 131I and 137Cs. The gamma camera evaluated in this work presents enough sensitivity to detect activities of such radionuclides at dose levels suitable to assess suspected accidental intakes.
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AUDINO, W F. SOUZA, W O. DANTAS, B M. Development of an in vitro bioassay technique for the determination of 65Zn in Biological Samples. Scientia plena vol. 8, 119904 (2012).
BERTELLI, L.; MELO D. R..; LIPSZTEIN J.; CRUZ-SUAREZ R..; “AIDE: Internal Dosimetry Software”, Radiation Protection Dosimetry, 130(3): 358–367, 2008
Dantas B.M., et al. A protocol for the calibration of gamma cameras to estímate internal contamination in emergency situations. Radiation Protection Dosimetry, Vol. 127, No. 1–4, pp. 253–257 (2007).
CENTERS FOR DISEASE CONTROL AND PREVENTION (CDC). Using Gamma Cameras to Assess Internal Contamination from Intakes of Radioisotopes. (2010).
IAEA - INTERNATIONAL ATOMIC ENERGY AGENCY. Methods for Assessing Occupational Radiation Doses due to Intakes of Radionuclides. Safety Report Series No. 37, Vienna, 2004.
COMISSÃO NACIONAL DE ENERGIA NUCLEAR (CNEN) – Norma NN 3.01 – Diretrizes Básicas de Proteção Radiológica. (2014).
CNEN – Comissão Nacional de Energia Nuclear. Número de Instalações Autorizadas. http://www.cnen.gov.br/instalacoes-autorizadas (acessado 28/07/2017).
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Derechos de autor 2021 Brazilian Journal of Radiation Sciences (BJRS)
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