ADIMIR DOS SANTOS

ADIMIR DOS SANTOS

(Fonte: Lattes)

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Possui graduação em Bacharelado Em Física pela Universidade de São Paulo (1975), mestrado em Reatores Nucleares de Potência e Tecnologia do Com pelo Instituto de Pesquisas Energéticas e Nucleares (1978) e doutorado em Nuclear Engineering pela University of Wisconsin – Madison (1984). Atualmente é PESQUISADOR TITULAR III do Instituto de Pesquisas Energéticas e Nucleares, professor titular da Universidade de São Paulo e Revisor de periódico da Progress in Nuclear Energy. Tem experiência na área de Engenharia Nuclear, com ênfase em Tecnologia dos Reatores. Atuando principalmente nos seguintes temas: SENSITIVITY ANALYSIS, TRANSMUTATION, THORIUM, U-233 BREEDING. (Texto extraído do Currículo Lattes em 28 set. 2021)

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Prediction of the power peaking factor in a boron-free small modular reactor based on a Support Vector Regression model and control rod bank positions
2021 - SANCHEZ, PRISCILA P.; SANTOS, ADIMIR dos
In order to ensure safety in a nuclear power plant, operation and protection systems must take into account safety parameters, whether to guide operators or to trip the reactor in emergency cases. Especially in a boron-free small modular reactor (SMR) where reactivity and power are controlled exclusively by rod banks, the power distribution is mostly influenced by its movements affecting the power peaking factor (PPF), which is an important parameter to be considered. The PPF relates the maximum local linear power density to the average power density in a fuel rod indicating a high neutron flux that can cause fuel rod damage. In this technical note, 2117 samples from simulations of an idealized boron-free SMR controlled exclusively by rod banks were used to generate a Support Vector Machine (SVM) model capable of estimating the PPF as a function of control rod bank positions. Such model could be used to predict the maximum PPF in the reactor core by carrying out simple calculation. Residing in a SVM parameter grid search and a 10-cross-validation process in the training set to reach an optimized and robust model, the results have shown a root-mean- squared error of about 0.1% consistent for both training and testing sets.
Impact of 235U resonance parameter evaluation in the reactivity prediction
2017 - LEAL, LUIZ; SANTOS, ADIMIR dos; IVANOV, EVGENY; IVANOVA, TATIANA
Resonance parameter evaluation of the U-235 cross sections using the Reich-Moore formalism was done with the computer code SAMMY from 0 to 2.25 keV to address issues with capture cross-section and standard fission cross-section values. The evaluation includes recent capture and fission cross-section measurements as well as high-resolution data used in previous U-235 evaluation. Moreover the new U-235 resonance parameter evaluation has been used in the calculation of a new benchmark experiment performed at the IPEN/MB-01 research reactor. The experiment, named the inversion point of the isothermal reactivity coefficient, is used to test temperature effects at low temperature. The results demonstrate that the new U-235 evaluation has greatly improved the prediction of reactivity temperature coefficient in contrast to previous evaluations. This paper is outlined in two parts, namely the first part deals with the description of the U-235 resonance analysis and evaluation up to 2.25 keV, and the second part presents the results of the isothermal reactivity coefficient calculations performed on the IPEN/MB-01 reactor.
A simple way to overcome the shortage of sup(3)He detectors in the IPEN/MB-01 nuclear reactor
2016 - GONNELLI, E.; PINTO, L.N.; LANDIM, H.R.; DINIZ, R.; JEREZ, R.; SANTOS, A. dos
In order to overcome the shortage of 3He detectors for subcritical experiments in the IPEN/MB-01 reactor, some experiments were performed employing less sensitive detectors, such as BF3, and a logic input module, which sums the counts from different detectors. Through microscopic and macroscopic neutron noise technique, it was possible to obtain, respectively, Rossi-α distribution and Auto Power Spectral Densities (APSD) for each detector configuration and various subcritical levels, and the prompt neutron decay constant (α) was extracted through a least squares procedure. In addition, Cross Power Spectral Densities (CPSD) were acquired for different types of detectors and the correlation among those detectors was confirmed. It was also observed that there was no loss of correlation among the neutron pulses, and therefore, the CPSD curves demonstrated the presence of correlated events. The α parameter was used as an indicator for the comparison of the results and for the quality of the experimental data. The obtained values demonstrate that the sum of counts technique does not present loss of information (correlated neutrons) even for different models and types of detectors, suggesting that the technique may be employed in neutron noise measurements for subcritical reactivity.