ROBERTO CARLOS DOS SANTOS
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Artigo IPEN-doc 24161 Technical feasibility study on volumetric reduction of radioactive wastes using plasma technology2017 - 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.Artigo IPEN-doc 24034 Time response measurements of rosemount pressure transmitters (model 3154) OF Angra I Power Plant2017 - SANTOS, ROBERTO C. dos; PEREIRA, IRACI M.; JUSTINO, MARCELO C.; SILVA, MARCOS C.This paper shows the Response of time five Rosemount model 3154N pressure trnasmiter from the Angra I Nuclear Power Plant. The tests were performed using the Hydraulic Ramp and Pressure Step Generator from the Sensor Response Time Measurement laboratory of CEN - Nuclear Engineering Center of IPEN. For each transmitter, damping was adjusted so that the time constant was less than or equal to 500 ms. This value has been determined so that the total value of the protection chain response time does not exceed the established maximum value of 2 seconds. For each transmitter ten tests were performed, obtaining mean values of time constant of 499.7 ms, 464.1 ms, 473.8 ms, 484.7 ms and 511.5 ms, with mean deviations 0.85%, 0.24%, 0.97%, 1.26% and 0.64% respectively.Relatório IPEN-doc 23416 Medida do tempo de resposta de transmissores de pressão da Usina Nuclear de Angra I2017 - PEREIRA, IRACI M.; SANTOS, ROBERTO C. dosNeste relatório são apresentados os resultados de Medida de Tempo de Resposta de cinco transmissores de pressão Rosemount modelo 3154N da Usina Nuclear de Angra I. Os testes foram realizados utilizando-se o Gerador Hidráulico de Rampa e Degrau de Pressão do laboratório de Medidas de Tempo de Resposta de Sensores do CEN – Centro de Engenharia Nuclear do IPEN. Para cada transmissor, foi feito o ajuste de damping para que a constante de tempo fosse menor ou igual a 500 ms. Este valor foi determinado para que o valor total de tempo de resposta da cadeia de proteção não ultrapasse o valor máximo estabelecido de 2 segundos. Para cada transmissor foram feitos dez testes, obtendo-se valores médios de constante de tempo de 499,7 ms, 464,1 ms, 473,8 ms, 484,7 e 511,5 ms, com desvios médios de 0,85%, 0,24%, 0,97%, 1,26% e 0,64% respectivamente.Resumo IPEN-doc 01962 Estudos do annealing de tracos de protons de energias entre 2 e 24 MeV em detectores polimeros Cr-391992 - PINHEIRO FILHO, J.D.; ALMEIDA, E.S.; BILBAO, E.Z.; SANTOS, R.C.; SILVA, A.X.; MORAES, S.B.; SCIANI, V.; RELA, P.R.Artigo IPEN-doc 12186 Time response measurements of angra I nuclear power plant using direct and indirect methodologies2007 - GONCALVES, IRACI M. P.; SANTOS, ROBERTO C. dos; LOPES, WAGNER J. dos R.; NAPOLITANO, OLIVIO da C.Estimation of sensor response characteristics is necessary to satisfy requirements on allowable response time for nuclear power plants. The methodology currently used includes direct and indirect measurements each of them having its vantages and disadvantages. The objective of this work is to compare the time response measurements of temperature and pressure sensors of the Brazilian Angra I nuclear power plant obtained using direct and indirect methodologies. Direct methods give more precise results, but need special equipments do be carried out and interfere with the reactor operation. Indirect methodology is most practical of being performed; it does not interfere with the reactor operation because the sensors do not have to be out of operation. On the other hand, since the parameter identification depends on the noise characteristics, there are cases where indirect methodology is not suitable to predict time response.Artigo IPEN-doc 10698 Process sensors characterization based on noise analysis techniques and artificial inteligence2005 - MESQUITA, R.N.; PERILLO, S.R.P.; SANTOS, R.C.Artigo IPEN-doc 15306 Time response of temperature sensors using neural networks2009 - SANTOS, ROBERTO C. dos; PEREIRA, IRACI M.Artigo IPEN-doc 07636 Response time measurement of temperature and pressure sensors of Angra-I nuclear power plant using noise analysis technique2001 - PERILLO, S.R.P.; GONCALVES, I.M.P.; SANTOS, R.C.; TING, D.K.S.Artigo IPEN-doc 17052 Time response prediction of brazilian nuclear power plant temperature sensors using neural networks2011 - SANTOS, ROBERTO C. dos; PEREIRA, IRACI M.Artigo IPEN-doc 06863 Time response measurement of temperature and pressure sensors of Angra-I nuclear power plant using Noise Analysis Technique2000 - PERILLO, S.R.P.; GONCALVES, I.M.P.; SANTOS, R.C.; TING, D.K.S.