JOSE CLAUDIO DELLAMANO

JOSE CLAUDIO DELLAMANO

(Fonte: Lattes)

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Graduate at Industrial Chemistry from Faculdades Oswaldo Cruz (1983), master's at Nuclear Tecnology from Instituto de Pesquisas Energéticas e Nucleares (1995) and Ph.D. at Tecnologia Nuclear from Instituto de Pesquisas Energéticas e Nucleares (2005). Has experience in Radiation Protection, Radioactive waste Management, Optimization in Radioprotection and Radiology. (Text obtained from the Currículo Lattes on October 14th 2021)

Graduado em Química Industrial pelas Faculdades Oswaldo Cruz (1983), Mestrado em Tecnologia Nuclear pelo Instituto de Pesquisas Energéticas e Nucleares - USP (1995) e Doutorado em Tecnologia Nuclear pelo Instituto de Pesquisas Energéticas e Nucleares - USP (2005). Atualmente é Professor do Curso Superior de Tecnologia em Radiologia do Centro Universitário Sant'Anna e Tecnologista do Instituto de Pesquisas Energéticas e Nucleares. Tem experiência em Radioproteção, Gestão de Rejeitos Radioativos, Otimização e Tecnologia em Radiologia, atuando principalmente nas áreas de Pesquisa, Desenvolvimento e Ensino. (Texto extraído do Currículo Lattes em 14 out. 2021)

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Analysis of accidents in industrial gammagraphy
2019 - DIAS, ANDRESSA de J.R.; VICENTE, ROBERTO; DELLAMANO, JOSE C.
This study presents industrial gammagraphy accidents from 1967 to 2015, as a way to help the improvement of knowledge to radiation protection and the prevention of futures accidents, based on its common causes. It is based on a research in progress. The term radiation protection is applied to the concept of protection of people, worker or public, against the harmful effect of ionizing radiation. It is an important area and has to be in constant improvement to gain the society’s trust. A way to make it possible is through studies of past accidents therefore, accidents reports are important. It is useful for creating a database with enough information to assist in accident management and prevention. This database also helps radiation practices to be more accepted by the community. From a public individual point of view, a practice with reliable statistics that shows low accident rates is more acceptable, even though some hazard might be present. The intent is gammagraphy’s risks to be managed and reduced in the future, so the use of the technology might grow while public’s acceptance increases and the magnitude of the perceived danger of the practice diminishes as seen through people’s eyes.
Borehole dimensions needed to fit the Brazilian inventory of disused radioactive sealed sources from lightning rods and smoke detectors
2019 - DELLAMANO, JOSE C.; HIROMOTO, GORO
Brazil has a large inventory of disused sealed radioactive sources (DSRS), accounting over two hundred thousands sources being safely stored at Brazilian National Nuclear Energy Commission institutes. The majority of them can not be disposed of in near surface repository due to long lived alpha emitters, mainly Ra 226 needles formerly used in brachytherapy and Am 241 sources from smoke detectors and lightning rods, which correspond to more than 90% of the total number of the sources currently stored. Therefore, an alternative strategy to dispose of these classes of DSRS is to adopt the IAEA Borehole Disposal Concept (BDC); in this sense, due to the usually small diameter of the disposal container, knowledge of the volume of each of these sources is needed. All Ra 226 needles and Am 241 sources from lightning rods do not have significant variations in geometry and size, but Am 241 sources from smoke detectors have more than 20 different sizes covering a range from a few millimeters to about sixty millimeters in length. Of course, this fact will strongly affect the borehole design. The main objective of this paper was to determine accurately the capacity of the BDC disposal capsules required to condition these sources as a function of the different diameters of the capsules. Results showed that the borehole linear extension necessary to fit the Brazilian inventory of Am 241 sources from lightning rods and smoke detectors can reach hundreds of meters, depending on the BDC capsule diameter chosen. These findings showed that the final destination of this class of DSRS of the Brazilian inventory should be carefully examinated.
Development of microwave technology for TENORM waste treatment - 17377
2017 - VICENTE, R.; TOLEDO, R.N.; REZENDE, R.; DELLAMANO, J.C.; MARUMO, J.T.
The sludge and scales generated by the oil and gas industry usually contain radionuclides of the thorium and uranium decay chains, the so-called technologically enhanced, naturally occurring radioactive materials (TENORM) waste. The handling of this waste must consider both the radiation risks presented by those radionuclides and its chemical toxicity, due to the decomposition of oil residues, which may generate hydrogen sulfide and other hazardous compounds. In the case of Brazil, Public Law 10.308 limits the management options for radioactive waste generated by offshore oil production rigs to drumming and storage; it prohibits disposal of any radioactive waste in seawaters, seabed or oceanic islands. This paper describes the results of the work to develop a treatment process using a specially designed microwave oven, which removes simultaneously water and hydrocarbons from the sludge, thus reducing the volume, the chemical toxicity and the chemical reactivity of the waste.
Technical feasibility study on volumetric reduction of radioactive wastes using plasma technology
2017 - PRADO, E.S.P.; DELLAMANO, J.C.; CARNEIRO, A.L.G.; SANTOS, R.C.; PETRACONI, G.; POTIENS JUNIOR, A.J.
The radioactive waste arising from nuclear reactors, hospitals, industry and research institutes are generated daily with a considerable amount. To final dispose of these radioactive waste safely and cost effectively, they must be transformed into physical and chemical compounds suitable for radionuclides immobilization with maximum volume and exhaust gaseous reduction. In this scope, among the promising technologies for the radioactive waste treatment, plasma technology allows reducing substantially the waste volume after exposing them to temperatures above 2,500ºC. In the planning and management of radioactive waste, the challenges related to plasma technology are presented as a motivation factor for the possible implantation of plasma reactors in nuclear plants and research centers aiming at improving the process of radioactive waste management.
Radioactive decay pattern of actinides present in waste from Mo-99 production
2017 - HIROMOTO, GORO; DELLAMANO, JOSE C.
Brazil is currently planning to produce 99Mo from fission of LEU targets to meet the present national demand of 99m Tc. The 99Mo activity planned at the end of irradiation is 5000 Ci (185 TBq) per weekly cycle, in order to meet the present demand of 1000 Ci (37 TBq) per week, after target cooling and processing. To predict the activities that will be handled in the waste treatment facility, the computational code SCALE 6.0 was used to simulate the irradiation of the uranium targets and the decay of radioactive products. This study presents the findings of this research, mainly focused on the actinides activity that will be present in the waste and the respective radioactive decay pattern over a period of one hundred thousand years.
Rejeitos radioativos gerados na produção de sup(99)Mo por fissão nuclear em função dos tempos de irradiação
2014 - HIROMOTO, GORO; DELLAMANO, JOSE C.
Limites de liberacao para rejeitos radioativos solidos
2005 - DELLAMANO, J.C.; SORDI, G.M.A.A.
Implementation of a computerized system for the management of radioactive lightning rods and smoke detectors
2013 - NASCIMENTO, RAFAEL A. do; DELLAMANO, JOSE C.; POTIENS JUNIOR, ADEMAR J.
Laser decontamination of the radioactive lightning rods
2012 - POTIENS JUNIOR, ADEMAR J.; DELLAMANO, JOSE C.; VICENTE, ROBERTO; WETTER, NIKLAUS U.; LANDULFO, EDUARDO; RAELE, MARCUS P.
Characterization of radioactive wastes - spent ion-exchange resins and charcoal filter beds
2009 - SILVA, ROZILENE E.; ISIKI, VERA L.K.; GOES, MARCOS M. de; POTIENS JUNIOR, ADEMAR J.; DELLAMANO, JOSE C.; VICENTE, ROBERTO