VALDIR DE SOUZA CARVALHO
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Artigo IPEN-doc 24425 Radioactive waste management Goiânia - São Paulo: 30 years later2017 - SOUZA, D.C.B. de; GERALDO, B.; TESSARO, A.P.G.; ROSTELATO, M.E.C.M.; MARUMO, J.T.; CARVALHO, V.S.; BARBOSA, N.K.O.; VICENTE, R.Considered the largest urban radiological accident in the world, the accident in Goiânia with Cesium-137 resulted in the death of four people and injuries in another 49, besides measurable levels of internal or exter-nal contamination in 129. The accident generated also environmental contamination and thousands of tons of radioactive waste that resulted from the response activities. The accident occurred as a result of the disman-tling of an equipment of radiotherapy by employees of a junkyard. Before the accident was identified, con-taminated materials were sent to recycling companies in the state of São Paulo. The objective of this work was to report the existence of waste from Goiânia accident in the state of São Paulo and to check the estimat-ed activities at the time of the waste conditioning by measuring the current dose rates in waste packages, allowing a refinement of previously applied calculations.Artigo IPEN-doc 24424 Evaluation of Exhaust System for Gaseous Waste from the Source Production Laboratory for Radiotherapy – IPEN2017 - SOUZA, D.C.B. de; COSTA, O.L.; FEHER, A.; GERALDO, B.; CARVALHO, V.S.; BARBOSA, N.K.O.; VICENTE, R.; ZEITUNI, C.A.; ROSTELATO, M.E.C.M.Exhaust systems in fume hood for chemicals and hazardous materials as radioactive substances are of great importance for the protection of the Occupationally Exposed Individual and the environment. They protect against external contam-inations by particulate matter, volatile and against inhalation of radioactive gases. This work intends to evaluate the exhaustion system of the Laboratory of Production of Radioactive Sources at the Nuclear and Energy Research Institute (IPEN).Artigo IPEN-doc 24374 Waste management protocols for iridium-192 sources production laboratory used in cancer treatment in Brazil2017 - ROSTELATO, M.E.C.M.; SOUZA, D.C.B.; SOUZA, C.D.; ZEITUNI, C.A.; VICENTE, R.; COSTA, O.L.; RODRIGUES, B.T.; MOURA, J.A.; FEHER, A.; MOURA, E.S.; MARQUES, J.R.O.; CARVALHO, V.S.; NOGUEIRA, B.R.Objective: The iridium-192 wired sources production results in radioactive waste that needs to follow the guidelines. The aim of this study is to do a radioactive waste management of wastes from iridium-192 sources production laboratory used in cancer treatment in Brazil. Methods: The wire is acquired in an alloy form with 80% platinum and 20% iridium encapsulated with 100%. Electronic microscopy, X-ray fluorescence, and posterior iridium neutron activation (to determine contaminants) are performed to ensure quality. A 50-cm twisted wire is placed in an aluminum tube. The tube is sealed and place inside the reactor irradiator system and is left for decay during 30 hours to wait for the others undesired activation products to decay. The wire is prepared for treatment with 48 cm length with 192 mCi maximum activity. All the equipment use inside the hot cell must be calibrated every four months. All the waste must be removed from the hot cell. Results: The solid waste is previously characterized in the analysis phase. The contaminants are already known and they are insignificant due to their fast half-life. The iridium-192 half-life is 74.2 days, classified as very short half-life waste. The reminiscent activity is 8mCi. Conclusion: The radioactive waste generated during the I192 wires production is solid, was a short half-life and a weakly activity of 9.7 GBq.g-1. According to the standards, this activity is too high to be discarded into the environment (limit 10 Bq.g-1). The waste must be managed by the R&R (retain e retard) system.Resumo IPEN-doc 15516 Calibration of surface radioactive contamination detectors with beta and alpha radiation2006 - POTIENS, M.P.A.; COSTA, A.M.; CARVALHO, V.S.; CALDAS, L.V.E.Artigo IPEN-doc 10959 Medicao da dose de radiacao beta absorvida em arranjo experimental para amostras biologicas utilizando TLDs2004 - MANZOLI, J.E.; CARVALHO, V.S.; CERQUEIRA, E.J.G.Artigo IPEN-doc 17123 Development and implementation of an automated system exchange attenuators of the OB85/1 gamma irradiator2011 - SILVA JUNIOR, IREMAR A.; RAMOS, MARCIO A.G.; CARVALHO, VALDIR S.; DINIZ, RAPHAEL E.; CESCON, CLAUDINEI T.; VIVOLO, VITOR; POTIENS, MARIA da P.A.Artigo IPEN-doc 15016 Study of the response of radiation protection monitors in terms of H*(10)in x radiation2009 - NONATO, FERNANDA B.C.; CARVALHO, VALDIR S.; VIVOLO, VITOR; CALDAS, LINDA V.E.Artigo IPEN-doc 11684 Absorbed dose measurements using TLDS in biological samples from beta radiation2006 - MANZOLI, JOSE E.; CARVALHO, VALDIR de S.; CERQUEIRA, ELIOMAR J.G. deArtigo IPEN-doc 18041 Comparison of calibration results for an extrapolation chamber obtained with different sup(90)Sr+sup(90)Y secondary standard sources2012 - ANTONIO, PATRICIA L.; CARVALHO, VALDIR S.; CALDAS, LINDA V.E.