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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Spallation product distributions and neutron multiplicities for accelerator-driven system using the CRISP code
2008 - PEREIRA, S.A.; DEPPMAN, A.; SILVA, G.; MAIORINO, J.R.; SANTOS, A. dos; DUARTE, S.B.; TAVARES, O.A.P.; GARCIA, F.
The inversion point of the isothermal reactivity coefficient of the IPEN/MB-01 reactor-II: theoretical Analysis
2005 - SANTOS, A.; ANDRADE e SILVA, G.S.; MENDONCA, A.G.; FUGA, R.; ABE, A.Y.
TORT, an SN three-dimensional transport code, is employed for the analysis of the inversion point of the isothermal reactivity coefficient of the IPEN/MB-01 reactor. The analyses are performed in companion NJOY, AMPX-II, and TORT systems considering the data libraries ENDF/B-VI.8, JENDL3.3, and JEF3.0. The analyses reveal that for this peculiar problem, there is a need to convert all the computer codes to DOUBLE-PRECISION as well as to increase to seven the number of digits of the ANISN library generated by XSDRNPM. Contrary to the traditional diffusion theory codes, TORT keff results are very sensitive to the number of both fine and broad groups. For instance, the traditional and very well known two- and four-group structure, largely utilized in several diffusion codes, produced simply unacceptable keff results. The highest deviation between calculated and experimental values found for the inversion point was –4.48°C. At first glance, there appears to be a significant discrepancy. However, in terms of reactivity coefficient, this discrepancy means a deviation of –0.90 ± 0.05 pcm/°C, which indicates that the calculational methodology and related nuclear data libraries meet the desired accuracy (–1.0 pcm/°C) for the determination of this parameter for thermal reactors.
Development of the CRISP package for spallation studies and accelerator-driven systems
2005 - ANEFALOS, S.; DEPPMAN, A.; SILVA, G.; MAIORINO, J.R.; SANTOS, A.; GARCIA, F.
Power generation from nuclear reactors provides an almost inexhaustive power source due to the huge quantities of nuclear fuel existent in our planet, which guarantees its utilization for thousands of years. Interest has been shifted to the so-called hybrid reactors [accelerator-driven systems (ADS)] as an alternative technology for power generation and transmutation, thus requiring precise knowledge about nuclear structure and nuclear reaction characteristics. Research groups from Instituto de Fisica, Universidade de São Paulo and Brazilian Center for Research in Physics made a joint effort to develop a computer program, CRISP, to calculate the intranuclear cascade proprieties and the nuclear evaporation process, present in all nuclear reactions with energies above a few tens of mega-electron-volts, using Monte Carlo techniques. Some reaction channels were included in these programs, resulting in a more realistic representation of the processes involved, aiming at reactor physics studies and academic studies about hadron and meson properties in nuclear matter. Some results obtained with this code and a comparison with experimental data are presented. Although all these results are preliminary, they are very consistent with the available experimental data. Since the applicability of the CRISP package has a wide range of options, especially in ADS, some results describing the effectiveness of the code were achieved.
A new human eye model for opthalmic brachytherapy dosimetry
2005 - YORIYAZ, HELIO; SANCHEZ, ANDREA; SANTOS, ADIMIR
Experimental determination of the decay constants and abundances of delayed neutrons by means of reactor noise analysis
2006 - DINIZ, RICARDO; SANTOS, ADIMIR
Absolute measurements of Betasub(eff) based on Rossi-alfa experiments and the two-region model in the IPEN/MB-01 research reactor
2008 - KURAMOTO, RENATO Y.R.; SANTOS, ADIMIR dos; JEREZ, ROGERIO; DINIZ, RICARDO
Physical models, cross sections, and numerical approximations used in MCNP and GEANT4 Monte Carlo codes for photon and electron absorbed fraction calculation
2009 - YORIYAZ, HELIO; MORALLES, MAURICIO; SIQUEIRA, PAULO de T.D.; GUIMARAES, CARLA da C.; CINTRA, FELIPE B.; SANTOS, ADIMIR dos
Purpose: Radiopharmaceutical applications in nuclear medicine require a detailed dosimetry estimate of the radiation energy delivered to the human tissues. Over the past years, several publications addressed the problem of internal dose estimate in volumes of several sizes considering photon and electron sources. Most of them used Monte Carlo radiation transport codes. Despite the widespread use of these codes due to the variety of resources and potentials they offered to carry out dose calculations, several aspects like physical models, cross sections, and numerical approximations used in the simulations still remain an object of study. Accurate dose estimate depends on the correct selection of a set of simulation options that should be carefully chosen. This article presents an analysis of several simulation options provided by two of the most used codes worldwide:MCNP and GEANT4. Methods: For this purpose, comparisons of absorbed fraction estimates obtained with different physical models, cross sections, and numerical approximations are presented for spheres of several sizes and composed as five different biological tissues. Results: Considerable discrepancies have been found in some cases not only between the different codes but also between different cross sections and algorithms in the same code. Maximum differences found between the two codes are 5.0% and 10%, respectively, for photons and electrons. Conclusion: Even for simple problems as spheres and uniform radiation sources, the set of parameters chosen by any Monte Carlo code significantly affects the final results of a simulation, demonstrating the importance of the correct choice of parameters in the simulation.