IRACI MARTINEZ PEREIRA GONCALVES

IRACI MARTINEZ PEREIRA GONCALVES

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Monitoring system for an experimental facility using GMDH methodology
2021 - PEREIRA, IRACI M.; MORAES, DAVI A.
This work presents a Monitoring System based on the GMDH - Group Method of Data Handling methodology applied in an Experimental Test Facility. GMDH is a combinatorial multi-layer algorithm in which a network of layers and nodes is generated using a number of inputs from the data stream being evaluated. The GMDH method is based on an underlying assumption that the data can be modeled by using an approximation of the Volterra Series or Kolmorgorov-Gabor polynomial. The Fault Test Experimental Facility was designed inspired in a PWR nuclear power plant and is composed by elements that correspond to the pressure vessel, steam generator, pumps of the primary and secondary reactor loops. The nuclear reactor core is represented by an electrical heater with different values of power. The exper-imental plant is fully instrumented with sensors and actuators. The Fault Test Experimental Facility can be operated to generate normal and faulty data. These failures can be added initially with small magnitude, and their magnitude being increasing gradually in a controlled way. The database will interface with the plant supervisory system SCADA (Super-visory Control and Data Acquisition) that provides the data through standard interface.
Time response measurements of rosemount pressure transmitters (model 3154) OF Angra I Power Plant
2017 - 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.
Monitoring system for an experimental facility using GMDH methodology
2017 - PEREIRA, IRACI M.; MORAES, DAVI A.; BUENO, ELAINE I.
This work presents a Monitoring System developed based on the GMDH - Group Method of Data Handling methodology to be used in an Experimental Test Facility. GMDH is a combinatorial multi-layer algorithm in which a network of layers and nodes is generated using a number of inputs from the data stream being evaluated. The GMDH network topology has been traditionally determined using a layer by layer pruning process based on a pre-selected criterion of what constitutes the best nodes at each level. The traditional GMDH method is based on an underlying assumption that the data can be modeled by using an approximation of the Volterra Series or Kolmorgorov-Gabor polynomial. The Fault Test Experimental Facility was designed to simulate a PWR nuclear power plant and is composed by elements that correspond to the pressure vessel, steam generator, pumps of the primary and secondary reactor loops. The nuclear reactor core is represented by an electrical heater with different values of power. The experimental plant will be fully instrumented with sensors and actuators, and the data acquisition system will be constructed in order to enable the details of the temporal analysis of process variables. The Fault Test Experimental Facility can be operated to generate normal and fault data. These failures can be added initially with small magnitude, and their magnitude being increasing gradually in a controlled way. The database will interface with the plant supervisory system SCADA (Supervisory Control and Data Acquisition) that provides the data through standard interface.
Neural networks used to monitor an experimental test workbench
2017 - MORAES, DAVI A.; PEREIRA, IRACI M.
This work presents the application of neural networks in an experimental workbench. This bench was developed with the purpose of conducting real time tests and data acquisition. The method applied for this work allowed to generate faulty data in a gradual and controlled way through the binary combination of double action valves. Using the SCADA application (Supervisory Control and Data Acquisition), it became possible to acquire data for analysis in Matlab / Simulink software. This bench has two reservoirs: a reservoir that has sensors for recording pressure and temperature variables for later analysis, and another reservoir that has level sensors. Four models were used to develop the respective practical experiments. In the first model, it was possible to perform all practical tests of the plant, as well as mechanical changes like repositioning of some mechanical components, piping, sensors and electrovalves. In the second model, it was noticed that the positioning of the flow meter, located after the pump output, prevented a good measurement of the flow variable. In the third model, it was perceived that the number of failures initially adopted, made the data too confusing for the neural network analysis. In the last model, it was possible to obtain a performance of 96.6% of hits after the reconfiguration for 4 controlled faults.
Medida do tempo de resposta de transmissores de pressão da Usina Nuclear de Angra I
2017 - PEREIRA, IRACI M.; SANTOS, ROBERTO C. dos
Neste 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.
Operator support system using computational intelligence techniques
2015 - BUENO, ELAINE I.; PEREIRA, IRACI M.
Development of a fault test experimental facility model using MATLAB
2015 - PEREIRA, IRACI M.; MORAES, DAVI A.
Ant colony optimization and neural networks applied to nuclear power plant monitoring
2015 - SANTOS, GEAN R. dos; ANDRADE, DELVONEI A. de; PEREIRA, IRACI M.
Time response measurements of angra I nuclear power plant using direct and indirect methodologies
2007 - GONCALVES, IRACI M. P.; SANTOS, ROBERTO C. dos; LOPES, WAGNER J. dos R.; NAPOLITANO, OLIVIO da C.
A theoretical model for the IPEN Research Reactor IEA-R1
2005 - GONCALVES, I.M.P.; TING, D.K.S.