Paulo de Tarso Dalledone Siqueira
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Paulo de Tarso Dalledone Siqueira has a total of 91 co-authors. Here are the top co-authors by number of shared publications:
Adimir dos Santos
5 shared publicationsHélio Yoriyaz
3 shared publications- Hélio Yoriyaz
Instituto de Pesquisas energéticas e Nucleares - IPEN-CNEN/SP, São Paulo, Brazil
3 shared publications Leda C. C. B. Fanaro
Instituto de Pesquisas Energéticas e Nucleares — IPEN/CNEN‐SP, 05508‐900 Butantã, Cidade Universitária, S.P., Brazil
3 shared publicationsRogério Jerez
Instituto de Pesquisas Energéticas e Nucleares — IPEN/CNEN‐SP, 05508‐900 Butantã, Cidade Universitária, S.P., Brazil
3 shared publications- Carlos José Soares
Department of Operative Dentistry and Dental Materials, School of Dentistry, Federal University of Uberlândia, Uberlândia, Brazil
2 shared publications
Latest Publications
- 24 March 2024
- Published by Elsevier in Applied Radiation and Isotopes
- Vol. 208, 111302
Thermal neutron dose measurements using TLD-100 detectors in the IPEN/MB-01 reactor core
- 24 March 2024
- Published by Elsevier in Applied Radiation and Isotopes
- Vol. 208, 111302
Thermal neutron dose measurements using TLD-100 detectors in the IPEN/MB-01 reactor core
- 27 November 2023
- Published by Elsevier in Brachytherapy
- Vol. 23 (1) , 73-84
Heterogeneous physical phantom for I-125 dose measurements and dose-to-medium determination
- 27 November 2023
- Published by Elsevier in Brachytherapy
- Vol. 23 (1) , 73-84
Heterogeneous physical phantom for I-125 dose measurements and dose-to-medium determination
- 14 November 2022
- Published by Elsevier in Brachytherapy
- Vol. 22 (1) , 80-92
A versatile physical phantom design and construction for I-125 dose measurements and dose-to-medium determination
- 14 November 2022
- Published by Elsevier in Brachytherapy
- Vol. 22 (1) , 80-92
A versatile physical phantom design and construction for I-125 dose measurements and dose-to-medium determination
- 1 August 2020
- Published by AIP Publishing in Review of Scientific Instruments
- Vol. 91 (8) , 083301
Neutron radiation effects on an electronic system on module
The NUMEN (NUclear Matrix Elements for Neutrinoless double beta decay) project was recently proposed with the aim to investigate the nuclear response to Double Charge Exchange reactions for all the isotopes explored by present and future studies of 0νββ decay. The expected level of radiation in the NUMEN experiment imposes severe limitations on the average lifetime of the electronic devices. During the experiments, it is expected that the electronic devices will be exposed to about 105 neutrons/cm2/s according to FLUKA simulations. This paper investigates the reliability of a System On Module (SOM) under neutron radiation. The tests were performed using thermal, epithermal, and fast neutrons produced by the Instituto de Pesquisas Energéticas e Nucleares 4.5 MW Nuclear Research Reactor. The results show that the National Instruments SOM is robust to neutron radiation for the proposed applications in the NUMEN project.
- 1 August 2020
- Published by AIP Publishing in Review of Scientific Instruments
- Vol. 91 (8) , 083301
Neutron radiation effects on an electronic system on module
The NUMEN (NUclear Matrix Elements for Neutrinoless double beta decay) project was recently proposed with the aim to investigate the nuclear response to Double Charge Exchange reactions for all the isotopes explored by present and future studies of 0νββ decay. The expected level of radiation in the NUMEN experiment imposes severe limitations on the average lifetime of the electronic devices. During the experiments, it is expected that the electronic devices will be exposed to about 105 neutrons/cm2/s according to FLUKA simulations. This paper investigates the reliability of a System On Module (SOM) under neutron radiation. The tests were performed using thermal, epithermal, and fast neutrons produced by the Instituto de Pesquisas Energéticas e Nucleares 4.5 MW Nuclear Research Reactor. The results show that the National Instruments SOM is robust to neutron radiation for the proposed applications in the NUMEN project.
- 1 June 2020
- Published by Elsevier in Applied Radiation and Isotopes
- Vol. 160, 109082
Correction factors for non-uniform large-area reference sources
- 1 June 2020
- Published by Elsevier in Applied Radiation and Isotopes
- Vol. 160, 109082
Correction factors for non-uniform large-area reference sources
- 6 July 2014
- Published by Springer Nature in Journal of Radioanalytical and Nuclear Chemistry
- Vol. 302 (1) , 17-26
Recalibration of U-doped standard glasses through uranium thin film for neutron-fluence measurements
- 6 July 2014
- Published by Springer Nature in Journal of Radioanalytical and Nuclear Chemistry
- Vol. 302 (1) , 17-26
Recalibration of U-doped standard glasses through uranium thin film for neutron-fluence measurements
- 22 May 2013
- Published by Elsevier in Annals of Nuclear Energy
- Vol. 60, 51-63
Validation of neutronic models and calculation systems by means of experimental results in the IPEN/MB-01 reactor
- 22 May 2013
- Published by Elsevier in Annals of Nuclear Energy
- Vol. 60, 51-63
Validation of neutronic models and calculation systems by means of experimental results in the IPEN/MB-01 reactor
- 1 March 2013
- Published by Elsevier in Radiation Measurements
- Vol. 50, 181-186
Boron thin films and CR-39 detectors in BNCT: A method to measure the 10B(n,α)7Li reaction rate
- 1 March 2013
- Published by Elsevier in Radiation Measurements
- Vol. 50, 181-186
Boron thin films and CR-39 detectors in BNCT: A method to measure the 10B(n,α)7Li reaction rate
- 13 October 2009
- Published by Wiley in Medical Physics
- Vol. 36 (11) , 5198-5213
Physical models, cross sections, and numerical approximations used inMCNPandGEANT4Monte Carlo codes for photon and electron absorbed fraction calculation
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:MCNPandGEANT4.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.
- 13 October 2009
- Published by Wiley in Medical Physics
- Vol. 36 (11) , 5198-5213
Physical models, cross sections, and numerical approximations used inMCNPandGEANT4Monte Carlo codes for photon and electron absorbed fraction calculation
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:MCNPandGEANT4.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.